From ac7ef3d86c7f470612259a5795cea71668249ffa Mon Sep 17 00:00:00 2001 From: shinkoo Date: Sun, 2 Oct 2022 03:27:18 +0200 Subject: [PATCH] 2011-10-03 --- exforall/403/40307.x4 | 328 +++++++++-- exforall/404/40409.x4 | 138 +++-- exforall/404/40457.x4 | 170 +++--- exforall/404/40468.x4 | 148 ++--- exforall/404/40490.x4 | 117 ++-- exforall/405/40501.x4 | 156 ++--- exforall/405/40506.x4 | 101 ++-- exforall/405/40510.x4 | 21 +- exforall/405/40568.x4 | 301 ++++++---- exforall/405/40581.x4 | 102 +++- exforall/407/40705.x4 | 92 +-- exforall/408/40834.x4 | 56 +- exforall/408/40851.x4 | 136 +++-- exforall/408/40860.x4 | 81 +-- exforall/408/40862.x4 | 117 ++-- exforall/408/40863.x4 | 75 ++- exforall/408/40873.x4 | 159 +++-- exforall/408/40874.x4 | 125 ++-- exforall/408/40890.x4 | 246 ++++---- exforall/409/40930.x4 | 166 +++--- exforall/409/40958.x4 | 118 ++-- exforall/409/40959.x4 | 216 ++++--- exforall/409/40968.x4 | 164 +++--- exforall/409/40969.x4 | 405 +++++++------ exforall/409/40986.x4 | 116 ++-- exforall/409/40987.x4 | 175 +++--- exforall/410/41044.x4 | 80 ++- exforall/411/41162.x4 | 141 +++-- exforall/411/41170.x4 | 103 ++-- exforall/411/41172.x4 | 121 +++- exforall/411/41183.x4 | 87 +-- exforall/411/41192.x4 | 147 +++-- exforall/411/41194.x4 | 82 +-- exforall/411/41197.x4 | 170 ++++-- exforall/412/41236.x4 | 68 +-- exforall/412/41272.x4 | 119 +++- exforall/412/41284.x4 | 240 ++++---- exforall/413/41318.x4 | 116 ++-- exforall/413/41322.x4 | 87 ++- exforall/413/41345.x4 | 136 +++-- exforall/413/41354.x4 | 76 ++- exforall/413/41374.x4 | 135 ++--- exforall/414/41438.x4 | 67 ++- exforall/414/41439.x4 | 184 ++++-- exforall/414/41460.x4 | 24 +- exforall/414/41487.x4 | 23 +- exforall/415/41508.x4 | 28 +- exforall/415/41551.x4 | 67 +++ exforall/415/41563.x4 | 33 +- exforall/415/41574.x4 | 80 +++ exforall/M00/M0036.x4 | 275 ++++----- exforall/M00/M0076.x4 | 128 ++-- exforall/M00/M0081.x4 | 110 ++-- exforall/M00/M0082.x4 | 82 +-- exforall/M00/M0087.x4 | 355 +---------- exforall/M00/M0089.x4 | 202 ++++--- exforall/M01/M0172.x4 | 104 ++-- exforall/M01/M0177.x4 | 165 +++--- exforall/M01/M0178.x4 | 263 +++++++-- exforall/M01/M0186.x4 | 34 +- exforall/M01/M0198.x4 | 150 +++-- exforall/M01/M0199.x4 | 57 +- exforall/M02/M0201.x4 | 110 ++-- exforall/M02/M0202.x4 | 59 +- exforall/M02/M0295.x4 | 380 +++++++++--- exforall/M02/M0296.x4 | 59 +- exforall/M02/M0297.x4 | 146 ++--- exforall/M02/M0298.x4 | 152 +++-- exforall/M02/M0299.x4 | 97 ++- exforall/M04/M0479.x4 | 40 +- exforall/M05/M0529.x4 | 58 +- exforall/M05/M0539.x4 | 190 +++--- exforall/M06/M0619.x4 | 136 ++--- exforall/M07/M0749.x4 | 33 +- exforall/M08/M0803.x4 | 63 ++ exforall/M08/M0804.x4 | 13 +- exforall/M08/M0807.x4 | 67 +++ exforall/M08/M0814.x4 | 122 ++++ exforall/M08/M0815.x4 | 148 +++++ exforall/M08/M0816.x4 | 840 ++++++++++++++++++++++++++ exforall/M08/M0817.x4 | 1295 +++++++++++++++++++++++++++++++++++++++++ exforall/M08/M0818.x4 | 55 ++ exforall/M08/M0819.x4 | 66 +++ exforall/M08/M0820.x4 | 69 +++ exforall/M08/M0821.x4 | 261 +++++++++ exforall/O00/O0077.x4 | 832 +++++++++++++++----------- exforall/O01/O0187.x4 | 411 ++++++------- exforall/O02/O0277.x4 | 525 +++++++++-------- exforall/O03/O0395.x4 | 596 +------------------ exforall/O04/O0443.x4 | 256 ++++---- exforall/O05/O0501.x4 | 137 +++-- exforall/O07/O0720.x4 | 47 +- exforall/O07/O0789.x4 | 108 +--- exforall/O10/O1033.x4 | 234 ++++---- exforall/O11/O1108.x4 | 40 +- exforall/O12/O1266.x4 | 47 +- exforall/O16/O1658.x4 | 212 ++++--- exforall/O18/O1891.x4 | 10 +- 98 files changed, 10415 insertions(+), 5867 deletions(-) create mode 100644 exforall/415/41551.x4 create mode 100644 exforall/415/41574.x4 create mode 100644 exforall/M08/M0803.x4 create mode 100644 exforall/M08/M0807.x4 create mode 100644 exforall/M08/M0814.x4 create mode 100644 exforall/M08/M0815.x4 create mode 100644 exforall/M08/M0816.x4 create mode 100644 exforall/M08/M0817.x4 create mode 100644 exforall/M08/M0818.x4 create mode 100644 exforall/M08/M0819.x4 create mode 100644 exforall/M08/M0820.x4 create mode 100644 exforall/M08/M0821.x4 diff --git a/exforall/403/40307.x4 b/exforall/403/40307.x4 index dbcfa2403..f4127931d 100644 --- a/exforall/403/40307.x4 +++ b/exforall/403/40307.x4 @@ -1,6 +1,6 @@ -ENTRY 40307 20101025 20110323 20110318 4151 -SUBENT 40307001 20101025 20110323 20110318 4151 -BIB 17 40 +ENTRY 40307 20110803 20111003 20110930 4153 +SUBENT 40307001 20110803 20111003 20110930 4153 +BIB 16 40 INSTITUTE (4RUSKUR) REFERENCE (J,YF,8,(6),1086,196812) (J,SNP,8,630,1969) Engl.translation of YF,8,(6),1086 . @@ -10,7 +10,7 @@ TITLE Elastic scattering of 4 MeV neutrons at small angles REL-REF (I,,G.V.Gorlov+,J,PTE,3,27,1966) FACILITY (VDG) Van De Graaff. INC-SOURCE (D-D) Deuteron-deuterium. Neutron flux is used at angle - 37 degrees (lab). + (POLNS) 37 degrees (lab). SAMPLE Cylinder with diameter 31 mm. Natural samples. METHOD Diff. elas. scat. c.-s. was measured using cylindrical geometry. @@ -22,15 +22,6 @@ MONITOR (82-PB-0(N,EL)82-PB-0,,DA) 20 degrees, which were measured absolutely. PART-DET (N) Neutrons. ADD-RES (COMP) Data are compared with theoretical calculation -STATUS (TABLE) Received from author 19760108 . - Data are given on Fig.3 of J,YF,8,(6),1086,1968 . -HISTORY (19760112C) Compiled at the center - (19760108R) - (20101025A) In Subents 003,005, 007, 009, 011,013: - data units were corrected PER-CENT -> NO-DIM, - data values were divided by 100. - BIB information was added. - DATA-ERR explanation was added. CORRECTION Diff. elas. scat. c.-s. is corrected on background modification at presence of sample (2-7 percent), multiple scattering in sample, contribution @@ -41,6 +32,15 @@ ERR-ANALYS (ERR-S,1.,3.) Statistical error is 1-3 %. 1.8 deg at 18-21deg angles. (DATA-ERR) Not defined when data were received. Probably statistical only. +HISTORY (19760112C) Compiled at the center + (19760108R) + (20101025A) In Subents 003,005, 007, 009, 011,013: + data units were corrected PER-CENT -> NO-DIM, + data values were divided by 100. + BIB information was added. + DATA-ERR explanation was added. + (20110810A) Subents 014-025 were added. + STATUS was moved in Subents 002-013 from Subent 001. ENDBIB 40 COMMON 3 3 EN EN-ERR ERR-1 @@ -48,11 +48,13 @@ MEV MEV PER-CENT 4.00 2.0000E-01 8. ENDCOMMON 3 ENDSUBENT 47 -SUBENT 40307002 20101025 20110323 20110318 4151 -BIB 1 2 +SUBENT 40307002 20110803 20111003 20110930 4153 +BIB 2 4 REACTION (29-CU-0(N,EL)29-CU-0,,DA) Diff. Elas. Scat. Cross Section. -ENDBIB 2 +STATUS (TABLE) Received from author 19760108 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 ANG DATA DATA-ERR @@ -66,13 +68,15 @@ ADEG B/SR B/SR 1.8000E+01 1.3000E+00 2.0000E-02 2.1000E+01 1.1700E+00 2.0000E-02 ENDDATA 10 -ENDSUBENT 17 -SUBENT 40307003 20101025 20110323 20110318 4151 -BIB 1 3 +ENDSUBENT 19 +SUBENT 40307003 20110803 20111003 20110930 4153 +BIB 2 5 REACTION (29-CU-0(N,EL)29-CU-0,,POL/DA,,ASY) Asymmetry of elas. scat. neutrons. -ENDBIB 3 +STATUS (TABLE) Received from author 19760108 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 5 NOCOMMON 0 0 DATA 3 7 ANG DATA DATA-ERR @@ -85,12 +89,14 @@ ADEG NO-DIM NO-DIM 1.8000E+01-0.0016 0.015 2.1000E+01 0.009 0.017 ENDDATA 9 -ENDSUBENT 17 -SUBENT 40307004 20101025 20110323 20110318 4151 -BIB 1 2 +ENDSUBENT 19 +SUBENT 40307004 20110803 20111003 20110930 4153 +BIB 2 4 REACTION (49-IN-0(N,EL)49-IN-0,,DA) Diff. elas. scat. cross-section. -ENDBIB 2 +STATUS (TABLE) Received from author 19760108 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 ANG DATA DATA-ERR @@ -104,13 +110,15 @@ ADEG B/SR B/SR 1.8000E+01 1.3200E+00 2.0000E-02 2.1000E+01 1.1400E+00 2.0000E-02 ENDDATA 10 -ENDSUBENT 17 -SUBENT 40307005 20101025 20110323 20110318 4151 -BIB 1 3 +ENDSUBENT 19 +SUBENT 40307005 20110803 20111003 20110930 4153 +BIB 2 5 REACTION (49-IN-0(N,EL)49-IN-0,,POL/DA,,ASY) Asymmetry of elas. scat. neutron. -ENDBIB 3 +STATUS (TABLE) Received from author 19760108 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 5 NOCOMMON 0 0 DATA 3 8 ANG DATA DATA-ERR @@ -124,12 +132,14 @@ ADEG NO-DIM NO-DIM 1.8000E+01 -0.0013 0.008 2.1000E+01 -0.0165 0.008 ENDDATA 10 -ENDSUBENT 18 -SUBENT 40307006 20101025 20110323 20110318 4151 -BIB 1 2 +ENDSUBENT 20 +SUBENT 40307006 20110803 20111003 20110930 4153 +BIB 2 4 REACTION (50-SN-0(N,EL)50-SN-0,,DA) Diff. elas. scat. cross section. -ENDBIB 2 +STATUS (TABLE) Received from author 19760108 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 ANG DATA DATA-ERR @@ -143,12 +153,14 @@ ADEG B/SR B/SR 1.8000E+01 1.3600E+00 2.0000E-02 2.1000E+01 1.1800E+00 2.0000E-02 ENDDATA 10 -ENDSUBENT 17 -SUBENT 40307007 20101025 20110323 20110318 4151 -BIB 1 2 +ENDSUBENT 19 +SUBENT 40307007 20110803 20111003 20110930 4153 +BIB 2 4 REACTION (50-SN-0(N,EL)50-SN-0,,POL/DA,,ASY) asymmetry of elas.scat.neutr. -ENDBIB 2 +STATUS (TABLE) Received from author 19760108 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 ANG DATA DATA-ERR @@ -162,12 +174,14 @@ ADEG NO-DIM NO-DIM 1.8000E+01-0.0013 0.008 2.1000E+01-0.0038 0.008 ENDDATA 10 -ENDSUBENT 17 -SUBENT 40307008 20101025 20110323 20110318 4151 -BIB 1 2 +ENDSUBENT 19 +SUBENT 40307008 20110803 20111003 20110930 4153 +BIB 2 4 REACTION (82-PB-0(N,EL)82-PB-0,,DA) Diff. elas. scat. cross section. -ENDBIB 2 +STATUS (TABLE) Received from author 19760108 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 ANG DATA DATA-ERR @@ -181,12 +195,14 @@ ADEG B/SR B/SR 1.8000E+01 4.5200E+00 8.0000E-02 2.1000E+01 3.9600E+00 8.0000E-02 ENDDATA 10 -ENDSUBENT 17 -SUBENT 40307009 20101025 20110323 20110318 4151 -BIB 1 2 +ENDSUBENT 19 +SUBENT 40307009 20110803 20111003 20110930 4153 +BIB 2 4 REACTION (82-PB-0(N,EL)82-PB-0,,POL/DA,,ASY) Asymmetry of elas.scat.neutr. -ENDBIB 2 +STATUS (TABLE) Received from author 19760108 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 ANG DATA DATA-ERR @@ -200,12 +216,14 @@ ADEG NO-DIM NO-DIM 1.8000E+01 0.0174 0.009 2.1000E+01 0.0174 0.01 ENDDATA 10 -ENDSUBENT 17 -SUBENT 40307010 20101025 20110323 20110318 4151 -BIB 1 2 +ENDSUBENT 19 +SUBENT 40307010 20110803 20111003 20110930 4153 +BIB 2 4 REACTION (83-BI-209(N,EL)83-BI-209,,DA) Diff. elas scat. cross section. -ENDBIB 2 +STATUS (TABLE) Received from author 19760108 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 ANG DATA DATA-ERR @@ -219,12 +237,14 @@ ADEG B/SR B/SR 1.8000E+01 4.4200E+00 8.0000E-02 2.1000E+01 3.8500E+00 8.0000E-02 ENDDATA 10 -ENDSUBENT 17 -SUBENT 40307011 20101025 20110323 20110318 4151 -BIB 1 2 +ENDSUBENT 19 +SUBENT 40307011 20110803 20111003 20110930 4153 +BIB 2 4 REACTION (83-BI-209(N,EL)83-BI-209,,POL/DA,,ASY) Asym. of elas.scat.neutr. -ENDBIB 2 +STATUS (TABLE) Received from author 1976-01-08 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 ANG DATA DATA-ERR @@ -238,12 +258,14 @@ ADEG NO-DIM NO-DIM 1.8100E+01 0.021 0.008 2.1000E+01 0. 0.008 ENDDATA 10 -ENDSUBENT 17 -SUBENT 40307012 20101025 20110323 20110318 4151 -BIB 1 2 +ENDSUBENT 19 +SUBENT 40307012 20110803 20111003 20110930 4153 +BIB 2 4 REACTION (92-U-0(N,EL)92-U-0,,DA) Diff. elas. scat. cross section. -ENDBIB 2 +STATUS (TABLE) Received from author 1976-01-08 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 ANG DATA DATA-ERR @@ -257,12 +279,14 @@ ADEG B/SR B/SR 1.8000E+01 4.5100E+00 8.0000E-02 2.1000E+01 3.7000E+00 7.0000E-02 ENDDATA 10 -ENDSUBENT 17 -SUBENT 40307013 20101025 20110323 20110318 4151 -BIB 1 2 +ENDSUBENT 19 +SUBENT 40307013 20110803 20111003 20110930 4153 +BIB 2 4 REACTION (92-U-0(N,EL)92-U-0,,POL/DA,,ASY) Asymmetry of elas.scat.neutr. -ENDBIB 2 +STATUS (TABLE) Received from author 19760108 . + Data are given on Fig.3 of J,YF,8,(6),1086,1968 . +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 ANG DATA DATA-ERR @@ -276,5 +300,185 @@ ADEG NO-DIM NO-DIM 1.8000E+01-0.006 0.009 2.1000E+01-0.0073 0.01 ENDDATA 10 -ENDSUBENT 17 -ENDENTRY 13 +ENDSUBENT 19 +SUBENT 40307014 20110803 20111003 20110930 4153 +BIB 2 4 +REACTION (29-CU-0(N,EL)29-CU-0,,DA,,,DERIV) + Diff. elas. scat. cross section at 0 deg. +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . + (DEP,40307002) Derived by extrapolation to 0 deg. +ENDBIB 4 +NOCOMMON 0 0 +DATA 3 1 +ANG DATA DATA-ERR +ADEG B/SR B/SR + 0. 1.66 0.13 +ENDDATA 3 +ENDSUBENT 12 +SUBENT 40307015 20110803 20111003 20110930 4153 +BIB 2 6 +REACTION 1(29-CU-0(N,TOT),,SIG) + Tot. cross section . + 2(29-CU-0(N,EL)29-CU-0,,AMP,,FCT) DATA is equal to + the imaginary part of the scattering amplitude at + zero angle which is equal K*SIGMA(TOT)/4PI +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . +ENDBIB 6 +NOCOMMON 0 0 +DATA 4 1 +DATA 1DATA-ERR 1DATA 2DATA-ERR 2 +B B CM CM +3.51 0.05 1.20E-12 0.02E-12 +ENDDATA 3 +ENDSUBENT 14 +SUBENT 40307016 20110803 20111003 20110930 4153 +BIB 2 4 +REACTION (49-IN-0(N,EL)49-IN-0,,DA,,,DERIV) + Diff. elas. scat. cross section at 0 deg. +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . + (DEP,40307004) Derived by extrapolation to 0 deg. +ENDBIB 4 +NOCOMMON 0 0 +DATA 3 1 +ANG DATA DATA-ERR +ADEG B/SR B/SR + 0. 1.98 0.16 +ENDDATA 3 +ENDSUBENT 12 +SUBENT 40307017 20110803 20111003 20110930 4153 +BIB 2 6 +REACTION 1(49-IN-0(N,TOT),,SIG) + Tot. cross section . + 2(49-IN-0(N,EL)49-IN-0,,AMP,,FCT) DATA is equal to + the imaginary part of the scattering amplitude at + zero angle which is equal K*SIGMA(TOT)/4PI +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . +ENDBIB 6 +NOCOMMON 0 0 +DATA 4 1 +DATA 1DATA-ERR 1DATA 2DATA-ERR 2 +B B CM CM +4.03 0.06 1.39E-12 0.02E-12 +ENDDATA 3 +ENDSUBENT 14 +SUBENT 40307018 20110803 20111003 20110930 4153 +BIB 2 4 +REACTION (50-SN-0(N,EL)50-SN-0,,DA,,,DERIV) + Diff. elas. scat. cross section at 0 deg. +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . + (DEP,40307006) Derived by extrapolation to 0 deg. +ENDBIB 4 +NOCOMMON 0 0 +DATA 3 1 +ANG DATA DATA-ERR +ADEG B/SR B/SR + 0. 2.01 0.16 +ENDDATA 3 +ENDSUBENT 12 +SUBENT 40307019 20110803 20111003 20110930 4153 +BIB 2 6 +REACTION 1(50-SN-0(N,TOT),,SIG) + Tot. cross section . + 2(50-SN-0(N,EL)50-SN-0,,AMP,,FCT) DATA is equal to + the imaginary part of the scattering amplitude at + zero angle which is equal K*SIGMA(TOT)/4PI +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . +ENDBIB 6 +NOCOMMON 0 0 +DATA 4 1 +DATA 1DATA-ERR 1DATA 2DATA-ERR 2 +B B CM CM +4.00 0.06 1.38E-12 0.02E-12 +ENDDATA 3 +ENDSUBENT 14 +SUBENT 40307020 20110803 20111003 20110930 4153 +BIB 2 4 +REACTION (82-PB-0(N,EL)82-PB-0,,DA,,,DERIV) + Diff. elas. scat. cross section at 0 deg. +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . + (DEP,40307008) Derived by extrapolation to 0 deg. +ENDBIB 4 +NOCOMMON 0 0 +DATA 3 1 +ANG DATA DATA-ERR +ADEG B/SR B/SR + 0. 7.09 0.57 +ENDDATA 3 +ENDSUBENT 12 +SUBENT 40307021 20110803 20111003 20110930 4153 +BIB 2 6 +REACTION 1(82-PB-0(N,TOT),,SIG) + Tot. cross section . + 2(82-PB-0(N,EL)82-PB-0,,AMP,,FCT) DATA is equal to + the imaginary part of the scattering amplitude at + zero angle which is equal K*SIGMA(TOT)/4PI +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . +ENDBIB 6 +NOCOMMON 0 0 +DATA 4 1 +DATA 1DATA-ERR 1DATA 2DATA-ERR 2 +B B CM CM +7.52 0.11 2.61E-12 0.04E-12 +ENDDATA 3 +ENDSUBENT 14 +SUBENT 40307022 20110803 20111003 20110930 4153 +BIB 2 4 +REACTION (83-BI-209(N,EL)83-BI-209,,DA,,,DERIV) + Diff. elas. scat. cross section at 0 deg. +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . + (DEP,40307010) Derived by extrapolation to 0 deg. +ENDBIB 4 +NOCOMMON 0 0 +DATA 3 1 +ANG DATA DATA-ERR +ADEG B/SR B/SR + 0. 6.97 0.56 +ENDDATA 3 +ENDSUBENT 12 +SUBENT 40307023 20110803 20111003 20110930 4153 +BIB 2 6 +REACTION 1(83-BI-209(N,TOT),,SIG) + Tot. cross section . + 2(83-BI-209(N,EL)83-BI-209,,AMP,,FCT) DATA is equal to + the imaginary part of the scattering amplitude at + zero angle which is equal K*SIGMA(TOT)/4PI +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . +ENDBIB 6 +NOCOMMON 0 0 +DATA 4 1 +DATA 1DATA-ERR 1DATA 2DATA-ERR 2 +B B CM CM +7.50 0.11 2.60E-12 0.04E-12 +ENDDATA 3 +ENDSUBENT 14 +SUBENT 40307024 20110803 20111003 20110930 4153 +BIB 2 4 +REACTION (92-U-0(N,EL)92-U-0,,DA,,,DERIV) + Diff. elas. scat. cross section at 0 deg. +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . + (DEP,40307012) Derived by extrapolation to 0 deg. +ENDBIB 4 +NOCOMMON 0 0 +DATA 3 1 +ANG DATA DATA-ERR +ADEG B/SR B/SR + 0. 7.43 .60 +ENDDATA 3 +ENDSUBENT 12 +SUBENT 40307025 20110803 20111003 20110930 4153 +BIB 2 6 +REACTION 1(92-U-0(N,TOT),,SIG) + Tot. cross section . + 2(92-U-0(N,EL)92-U-0,,AMP,,FCT) DATA is equal to + the imaginary part of the scattering amplitude at + zero angle which is equal K*SIGMA(TOT)/4PI +STATUS (TABLE) Table 2 of J,YF,8,(6),1086,1968 . +ENDBIB 6 +NOCOMMON 0 0 +DATA 4 1 +DATA 1DATA-ERR 1DATA 2DATA-ERR 2 +B B CM CM +7.81 0.12 2.71E-12 0.04E-12 +ENDDATA 3 +ENDSUBENT 14 +ENDENTRY 25 diff --git a/exforall/404/40409.x4 b/exforall/404/40409.x4 index 075099e13..cdf223862 100644 --- a/exforall/404/40409.x4 +++ b/exforall/404/40409.x4 @@ -1,35 +1,65 @@ -ENTRY 40409 850423 20050926 0000 -SUBENT 40409001 850423 20050926 0000 -BIB 13 16 +ENTRY 40409 20110810 20111003 20110930 4153 +SUBENT 40409001 20110810 20111003 20110930 4153 +BIB 13 36 INSTITUTE (4ZZZDUB) -REFERENCE (C,73KIEV,2,160,7305) -AUTHOR (I.KWITEK,Z.KOSINA,JA.BISHOPH,Z.DLOUGI,J.P.POPOV) -TITLE ALPHA-ENERGY-SPECTRUM STUDY FROM THE REACTION - ND-143(N,ALPHA)CE-140 ON THERMAL NEUTRONS -INC-SOURCE (REAC) -INC-SPECT REACTOR SPECTRUM -SAMPLE OXIDE, ND-143 ENRICHMENT 83.2 PERCENT, THICKNESS 6 - MICROMETERS, AREA 5*5 CM-SQ -METHOD NO INFORMATION -DETECTOR (SOLST) SILICIUM SEMICONDUCTOR DETECTORS -MONITOR (60-ND-143(N,A)58-CE-140,,SIG) FOR E=9.43 EV +COMMENT Information about institute is absent in the article. +REFERENCE (C,73KIEV,2,160,197305) +AUTHOR (I.Kvitek,Z.Kosina,Ya.Bishoph,Z.Dlougi,Yu.P.Popov) +TITLE Alpha-energy-spectrum study from the reaction + Nd-143(N,ALPHA)Ce-140 on thermal neutrons +INC-SOURCE (REAC) WWR-S . +INC-SPECT Reactor spectrum 1.E+8 n/sec/cm**2. + Cd ratio about 5.5 . +SAMPLE Oxide, Nd-143 enrichment 83.2 %, thickness 6 + micrometers, area 5*5 cm**2, on Al backing of 6 microm +METHOD (EDE) Measurement during 355 hr with two different + samples at 4 MW reactor power. + Background was measured by Cd filter in neutron beam + during 90 hr. + Measurement during 760 hr at 2 MW reactor power with + different E-detector. +DETECTOR (TELES,SIBAR) Two silicon semiconductor detectors: + deltaE detector of 13 microm thickness, 1 cm**2 area; + E detector of barrier thickness about 100 microm, + 0.5 or 1 cm**2 area. + Energy calibration by + - Am-241 alpha-source (5.48 MeV), energy resolution + 85 keV; + - monitor reaction; + - n,alpha reaction on boron admixture in sample. EN-SEC (E,A) -HISTORY (790903C) COMPILED IN THE CENTER - (840210U) MONIT-REF EXCLUDED -ERR-ANALYS (DATA-ERR) NOT SPECIFIED -ENDBIB 16 +CORRECTION For contribution of high resonances < 5 %. +HISTORY (19790903C) Compiled in the center + (19840210U) MONIT-REF excluded + (20110810A) M.M. Subent 004 : reaction coding was moved + in proper position. + Upper -> lower case correction. + Dates were corrected for 4-digits year. + BIB, COMMON information was added. + COMMENT was added. +ENDBIB 36 +COMMON 1 3 +EN-DUMMY +EV + 2.5300E-02 +ENDCOMMON 3 +ENDSUBENT 43 +SUBENT 40409002 20110810 20111003 20110930 4153 +BIB 5 8 +REACTION (60-ND-143(N,A)58-CE-140,PAR,SIG,,MXW) For specific + energy of alphas +MONITOR (60-ND-143(N,A)58-CE-140,PAR,SIG) For E=9.43 MeV . + FWHM of 9.43 MeV peak - 130 keV in this measurement. +MONIT-REF (12057001,N.S.Oakey+,J,PL/B,26,662,1968) +ERR-ANALYS (DATA-ERR) Monitor error is not included. +STATUS (TABLE) Table 1 of C,73KIEV,2,160,1973. + (SPSDD,30421002) Superseded by newer re-measured data. +ENDBIB 8 COMMON 2 3 -EN-DUMMY MONIT -EV MB - 2.5300E-02 2.1280E+01 +MONIT E-NRM +MB MEV + 21.28 9.43 ENDCOMMON 3 -ENDSUBENT 23 -SUBENT 40409002 850423 20050926 0000 -BIB 1 2 -REACTION (60-ND-143(N,A)58-CE-140,PAR,SIG) FOR SPECIFIC ENERGY - OF ALPHAS -ENDBIB 2 -NOCOMMON 0 0 DATA 5 3 E E-MIN E-MAX DATA DATA-ERR MEV MEV MEV MB MB @@ -37,25 +67,41 @@ MEV MEV MEV MB MB 7.6000E+00 3.7000E-01 7.0000E-02 7.0000E+00 7.2000E+00 1.3000E-01 6.0000E-02 ENDDATA 5 -ENDSUBENT 12 -SUBENT 40409003 850423 20050926 0000 -BIB 1 1 -REACTION (60-ND-143(N,G+A)58-CE-140,SEQ/PAR,SIG) -ENDBIB 1 -NOCOMMON 0 0 -DATA 3 1 -E DATA DATA-ERR -MEV MB MB - 8.6000E+00 9.0000E-01 1.0000E-01 +ENDSUBENT 22 +SUBENT 40409003 20110810 20111003 20110930 4153 +BIB 6 9 +REACTION (60-ND-143(N,A)58-CE-140,PAR,SIG,G,MXW) +MONITOR (60-ND-143(N,A)58-CE-140,PAR,SIG) For E=9.43 MeV . + FWHM of 9.43 MeV peak - 130 keV in this measurement. +MONIT-REF (12057001,N.S.Oakey+,J,PL/B,26,662,1968) +REL-REF (D,12057002,N.S.Oakey+,J,PL/B,26,662,1968) + Three times higher than data of N.S.Oakey+ . +ERR-ANALYS (DATA-ERR) Monitor error is not included. +STATUS (TABLE) Table 1 of C,73KIEV,2,160,1973. + (SPSDD,30421003) Superseded by newer re-measured data. +ENDBIB 9 +COMMON 2 3 +MONIT E-NRM +MB MEV + 21.28 9.43 +ENDCOMMON 3 +DATA 4 1 +E E-RSL-FW DATA DATA-ERR +MEV MEV MB MB + 8.6000E+00 0.77 0.90 0.10 ENDDATA 3 -ENDSUBENT 9 -SUBENT 40409004 850423 20050926 0000 -BIB 2 3 -REACTION (60-ND-143(N,A)58-CE-140,,DE) -STATUS (UNOBT) DATA GIVEN ON A GRAPH - NUMERICAL DATA ARE NOT AVAILABLE -ENDBIB 3 +ENDSUBENT 21 +SUBENT 40409004 20110810 20111003 20110930 4153 +BIB 3 7 +REACTION (60-ND-143(N,A)58-CE-140,,DE,,MXW/RAW) + Energy spectrum of alpha-particles is given as counts. +CORRECTION Alpha-background (normalized in 5.5-6.7 energy range) + due to Al(N,A) reaction was subtracted. +STATUS (UNOBT) Data given on Fig.3 of C,73KIEV,2,160,1973. + Numerical data are not available + (SPSDD,30277002) Superseded by newer re-measured data. +ENDBIB 7 NOCOMMON 0 0 NODATA 0 0 -ENDSUBENT 7 +ENDSUBENT 11 ENDENTRY 4 diff --git a/exforall/404/40457.x4 b/exforall/404/40457.x4 index c33bff491..0d06d8321 100644 --- a/exforall/404/40457.x4 +++ b/exforall/404/40457.x4 @@ -1,65 +1,76 @@ -ENTRY 40457 850329 20050926 0000 -SUBENT 40457001 850329 20050926 0000 -BIB 14 24 -INSTITUTE (4CCPFEI) -REFERENCE (J,AE,43,(4),266,7710) - (P,YFI-25,30,7711) - (R,FEI-577,75) EXPERIMENTAL DETAILS -AUTHOR (V.JA.BARYBA,B.V.ZHURAVLJOV,N.V.KORNILOV, - O.A.SAL'NIKOV) -TITLE ANGULAR AND ENERGETIC DISTRIBUTION OF NEUTRONS - EMITTED BY BOMBARDMENT OF U-238 BY 2-47 MEV NEUTRONS -FACILITY (CYCTM) TANDEM CYCLOTRON EGP-10M, BEAM ENERGY 10. MEV - PULSE DURATION 2. NSEC - PULS-REPETITION RATE 5.0 MEGAHERTZ -INC-SOURCE (P-T) -SAMPLE HOLLOW METALLIC CYLINDERS, INNER,DIAM. 19.9 TO 14.9 - MM,OUTER DIAM. 22.6 MM, HEIGHT CIRCA 49. MM - OUTER DIAM 22.6 MM HEIGHT CIRCA 49 MM -METHOD (TOF) -DETECTOR (SOLST) SOLID STATE DETECTOR WITH STILBENE CRYSTAL - FOR NEUTRON DETECTION - (SCIN) FOR NEUTRON MONITORING -MONITOR ABSOLUTE MEASUREMENTS, EXCEPT FOR SIGMA(INL) SUB 002 -STATUS FROM PUBLISHED SOURCES LISTED UNDER 'REFERENCE' -HISTORY (781121C) COMPILED AT THE CENTRE -CORRECTION MULTIPLE SCATTERING CORRECTION IS 30. PERCENT -ERR-ANALYS (DATA-ERR) TOTAL ERROR -ENDBIB 24 +ENTRY 40457 20110712 20111003 20110930 4153 +SUBENT 40457001 20110712 20111003 20110930 4153 +BIB 12 30 +INSTITUTE (4RUSFEI) +REFERENCE (J,AE,43,(4),266,197710) + (J,SJA,43,(4),899,1977) Engl. translation of J,AE,43 . + #doi:10.1007/BF01117994 + (P,YFI-25,30,197711) + (R,FEI-577,1975) Experimental details +AUTHOR (V.Ya.Baryba,B.V.Zhuravlev,N.V.Kornilov, + O.A.Sal'nikov) +TITLE Energy and angular distributions of neutrons produced + in the bombardment of U-238 with 2.47 MeV neutrons +FACILITY (CYCTM) Tandem cyclotron EGP-10M, beam energy 10. MeV + pulse duration 2. nsec + pulse-repetition rate 5.0 MegaHertz +INC-SOURCE (P-T) Solid tritium target of 1.5 mg. +SAMPLE Hollow metallic cylinders, + inner diam. 19.9,17.6,14.9 mm, + outer diam. 22.6,22.5,22.5 mm, + height 48.7,49.2,48.9 mm. +METHOD (TOF) 197 cm flight base. +DETECTOR (SOLST) Solid state detector with stilbene crystal of + diam. 70 mm, height 50 mm -for neutron detection. + (SCIN) For neutron beam monitoring . +MONITOR (98-CF-252(N,F),PR,NU/DE) For detector efficiency. + Cf-252 prompt neutron spectrum was described by Terrell + formula of T=1.42 MeV. +HISTORY (19781121C) Compiled at the centre + (20110712A) Upper -> lower case correction. + Dates were corrected for 4-digits year. + Ref. J,SJA was added. +CORRECTION Multiple scattering correction is 30. percent +ENDBIB 30 COMMON 2 3 EN EN-RSL MEV KEV - 2.4700E+00 1.0000E+02 + 2.47 100. ENDCOMMON 3 -ENDSUBENT 31 -SUBENT 40457002 850329 20050926 0000 -BIB 5 10 +ENDSUBENT 37 +SUBENT 40457002 20110712 20111003 20110930 4153 +BIB 6 14 REACTION (92-U-238(N,INL)92-U-238,PAR,SIG) MONITOR 1(92-U-238(N,F),,SIG) 2(92-U-238(N,F),,NU) -MONIT-REF 2(40429003,NURPEISOV+,R,FEI-543,74) -STATUS (DEP,40457003) DATA OBTAINED FROM SUBENT 40457003 -ERR-ANALYS (DATA-ERR) TOTAL ERROR - (DATA-ERR1) ERROR DUE TO THE POLYNOMIAL REPRESENTATION - (DATA-ERR2) ERROR DUE TO ANGULAR DISTRIBUTION - (DATA-ERR3) ERROR DUE TO NORMALIZATION - (DATA-ERR4) INTEGRATION ERROR -ENDBIB 10 -COMMON 6 3 -Q-VAL-MIN Q-VAL-MAX DATA-ERR1 DATA-ERR2 DATA-ERR3 DATA-ERR4 -MEV MEV PER-CENT PER-CENT PER-CENT PER-CENT --1.3500E+00-9.0000E-01 2.0000E+00 6.0000E+00 5.0000E+00 4.0000E+00 +MONIT-REF 2(40429003,V.Nurpeisov+,R,FEI-543,1974) + 1(,M.N.Nikolaev+,R,YK-8,(1),10,1972) Yad.Const.,8,part1. +ANALYSIS (INTAD) +STATUS (DEP,40457003) Data obtained from SUBENT 40457003 + (TABLE) Text, page 67, of J,AE,43,(4),266,1977. + = text,page 31, of P,YFI-25,30,1977. +ERR-ANALYS (DATA-ERR) Total error + (DATA-ERR1) Error due to the polynomial representation + (DATA-ERR2,4.,6.) Error due to angular distribution + (DATA-ERR3) Error due to normalization + (DATA-ERR4) Integration error +ENDBIB 14 +COMMON 5 3 +Q-VAL-MIN Q-VAL-MAX DATA-ERR1 DATA-ERR3 DATA-ERR4 +MEV MEV PER-CENT PER-CENT PER-CENT +-1.3500E+00-9.0000E-01 2. 5. 4. ENDCOMMON 3 DATA 4 1 DATA DATA-ERR MONIT1 MONIT2 -MB MB B NO-DIM +MB MB B PRT/FIS 3.8000E+02 2.5000E+01 5.5000E-01 2.6600E+00 ENDDATA 3 -ENDSUBENT 22 -SUBENT 40457003 850329 20050926 0000 -BIB 1 1 +ENDSUBENT 26 +SUBENT 40457003 20110712 20111003 20110930 4153 +BIB 2 2 REACTION (92-U-238(N,INL)92-U-238,PAR,DA) -ENDBIB 1 +STATUS (TABLE) Table 1 of P,YFI-25,30,1977 +ENDBIB 2 COMMON 2 3 Q-VAL-MIN Q-VAL-MAX MEV MEV @@ -74,15 +85,19 @@ ADEG MB/SR MB/SR 1.2000E+02 2.8100E+01 1.2000E+00 1.5000E+02 2.7200E+01 1.4000E+00 ENDDATA 7 -ENDSUBENT 17 -SUBENT 40457004 850329 20050926 0000 -BIB 3 5 +ENDSUBENT 18 +SUBENT 40457004 20110712 20111003 20110930 4153 +BIB 4 9 REACTION (92-U-238(N,INL)92-U-238,PAR,DA,N,LEG/RSD) -COMMENT CROSS-SECTION HAS FOLLOWING REPRESENTATION +COMMENT Cross-section has following representation (D-SIG(TETA)/D-OMEGA)/(D-SIG(90)/D-OMEGA)= 1/4PI*(A(0)+SUM(A(L)P(L))) -STATUS (DEP,40457003) DATA OBTAINED FROM SUBENT 40457003 -ENDBIB 5 +STATUS (DEP,40457003) Data obtained from SUBENT 40457003 + (TABLE) Text, page 67, of J,AE,43,(4),266,1977. + = text,page 31, of P,YFI-25,30,1977. +HISTORY (20110712A) M.M. "N" was deleted from SF7 according to + the comment of N.Otsuka (NDS IAEA). +ENDBIB 9 COMMON 2 3 Q-VAL-MIN Q-VAL-MAX MEV MEV @@ -91,27 +106,38 @@ ENDCOMMON 3 DATA 3 3 NUMBER DATA DATA-ERR NO-DIM NO-DIM NO-DIM - 0.0000E+00 1.2570E+01 2.3000E-01 - 1.0000E+00 1.7700E+00 3.6000E-01 - 2.0000E+00 5.9000E-01 5.0000E-01 + 0. 1.2570E+01 2.3000E-01 + 1. 1.7700E+00 3.6000E-01 + 2. 5.9000E-01 5.0000E-01 ENDDATA 5 -ENDSUBENT 19 -SUBENT 40457005 850329 20050926 0000 -BIB 2 6 -REACTION (92-U-238(N,F),,DA,N,LEG/RSD) ANGULAR DISTRIBUTION - OF FISSION NEUTRONS - IN THE ENERGY RANGE - 3. - 9. MEV -COMMENT WITHIN 4-PERCENT ACCURACY ANGULAR DISTRIBUTION - OF FISSION NEUTRONS IS ISOTROPIC -ENDBIB 6 +ENDSUBENT 23 +SUBENT 40457005 20110712 20111003 20110930 4153 +BIB 4 17 +REACTION (92-U-238(N,F),,DA,N,LEG/RSD) Angular distribution + of fission neutrons + in the energy range + 3. - 9. MeV +ADD-RES (N-SPC) Fission neutron spectra were described by + Maxwellian distribution with T ,MeV : + Angle Sample 2 Sample 3 + 30. 1.31+-0.05 + 60. 1.36+-0.05 + 90. 1.28+-0.04 1.32+-0.04 + 120. 1.38+-0.05 + 150. 1.33+-0.04 + Average =1.33+-0.04 MeV, + average =3/2*=1.995+-0.060 MeV. +COMMENT Within 4-percent accuracy - angular distribution + of fission neutrons is isotropic +STATUS (TABLE) Text, page 67, of J,AE,43,(4),266,1977. +ENDBIB 17 NOCOMMON 0 0 DATA 3 3 NUMBER DATA DATA-ERR NO-DIM NO-DIM NO-DIM - 0.0000E+00 1.2660E+01 1.5000E-01 - 1.0000E+00-2.7000E-01 2.2000E-01 - 2.0000E+00 9.0000E-02 3.0000E-01 + 0. 1.2660E+01 1.5000E-01 + 1. -2.7000E-01 2.2000E-01 + 2. 9.0000E-02 3.0000E-01 ENDDATA 5 -ENDSUBENT 16 +ENDSUBENT 27 ENDENTRY 5 diff --git a/exforall/404/40468.x4 b/exforall/404/40468.x4 index c1dba469b..bfbc1bdbd 100644 --- a/exforall/404/40468.x4 +++ b/exforall/404/40468.x4 @@ -1,44 +1,46 @@ -ENTRY 40468 881020 20050926 0000 -SUBENT 40468001 881020 20050926 0000 -BIB 12 22 -TITLE RESONANCE PARAMETERS OF ISOTOPES CS-133 AND CS-134 - IN THE ENERGY RANGE UP TO 400 EV -AUTHOR (V.A.ANUFRIEV,T.S.BELANOVA,S.I.BABICH,YU.S.ZAMYATNIN, - A.G.KOLESOV,E.I.SKOKOV,S.M.KALEBIN,V.S.ARTAMONOV, - R.N.IVANOV,YU.B.NOVIKOV) -INSTITUTE (4CCPNIR,4CCPITE) -REFERENCE (C,76LOWELL,,7607) DATA ARE GIVEN -MONITOR ABSOLUTE MEASUREMENT -METHOD (TOF) TIME-OF-FLIGHT METHOD WITH RESOLUTION 70 NSEC/M -DETECTOR (PROPC) BATTERY OF HE-3 PROPORTIONAL COUNTERS, -INC-SOURCE (REAC) REACTOR -PART-DET (N) NEUTRONS -ANALYSIS (SHAPE) SHAPE ANALYSIS UP TO NEUTRON ENERGY OF 50 EV. - (AREA) AREA ANALYSIS OVER 50 EV. -ERR-ANALYS (ERR-S) MAXIMAL STATISTICAL ERROR - (ERR-1) MINIMAL STATISTICAL ERROR - (ERR-2) MAXIMAL ERROR OF THE BACKGROUND -HISTORY (770404C) COMPILED AT THE CENTRE - (881020U) SEVERAL OBSOLETE KEYWORDS CHANGED, NUMERICAL - ERRORS CORRECTED AND ISO-QUANT INTO REACTION CONVERTED - DATA-ERR HEADING INTO ERR-T CHANGED, ERROR STRUCTURE - IS GIVEN AND SEVERAL AUTHOR NAMES CORRECTED -ENDBIB 22 -COMMON 3 3 -ERR-S ERR-1 ERR-2 -PER-CENT PER-CENT PER-CENT - 1.5 0.5 4. -ENDCOMMON 3 -ENDSUBENT 29 -SUBENT 40468002 881020 20050926 0000 -BIB 3 6 -REACTION 1(55-CS-133(N,0),,EN) RESONANCE ENERGY. - 2(55-CS-133(N,TOT),,WID) TOTAL WIDTH OF RESONANCE. - 3(55-CS-133(N,EL),,WID,,2G) 2G*NEUTR.-W.OF RESONANCE. -SAMPLE SAMPLE THICKNESS IS 9.514*10**21 NUCLEI/CM**2. -STATUS (DEP,40468004) DATA ARE OBTAINED BY ANALYSING OF DATA - (DEP,40468005) FROM SUBENTS 40468004 AND 40468005 -ENDBIB 6 +ENTRY 40468 20110816 20111003 20110930 4153 +SUBENT 40468001 20110816 20111003 20110930 4153 +BIB 12 25 +TITLE Resonance parameters of isotopes Cs-133 and Cs-134 + in the energy range up to 400 eV +AUTHOR (V.A.Anufriev,T.S.Belanova,S.I.Babich,Yu.S.Zamyatnin, + A.G.Kolesov,E.I.Skokov,S.M.Kalebin,V.S.Artamonov, + R.N.Ivanov,Yu.B.Novikov) +INSTITUTE (4RUSNIR,4RUSFEI) +REFERENCE (C,76LOWELL,,197607) Data are given +METHOD (TOF) Time-of-flight method with resolution 70 nsec/m +DETECTOR (PROPC) Battery of He-3 proportional counters. +FACILITY (REAC,4RUSNIR) Reactor +INC-SOURCE (REAC) +PART-DET (N) Neutrons +ANALYSIS (SHAPE) Shape analysis up to neutron energy of 50 eV. + (AREA) Area analysis over 50 eV. +ERR-ANALYS (ERR-S,0.5,1.5) Statistical error + (ERR-1,,4.) Maximal error of the background +HISTORY (19770404C) Compiled at the centre + (19881020U)Several obsolete keywords changed, numerical + errors corrected and ISO-QUANT into REACTION converted + DATA-ERR heading into ERR-T changed, error structure + is given and several author names corrected. + (20110816A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + SPSDD was added in Subents 002, 003 . + REACTION was corrected in Subents 004,005. +ENDBIB 25 +NOCOMMON 0 0 +ENDSUBENT 28 +SUBENT 40468002 20110816 20111003 20110930 4153 +BIB 3 9 +REACTION 1(55-CS-133(N,0),,EN) Resonance energy. + 2(55-CS-133(N,TOT),,WID) Total width of resonance. + 3(55-CS-133(N,EL),,WID,,2G) 2G*neutr.-W.of resonance. +SAMPLE Sample thickness is 9.514*10**21 nuclei/cm**2. +STATUS (DEP,40468004) Data are obtained by analyzing of data + (DEP,40468005) from SUBENTS 40468004 and 40468005 . + (SPSDD,41284002) Superseded by newer publication of + data for three samples including also this one. + (TABLE) From C,76LOWELL,,1976 +ENDBIB 9 COMMON 1 3 MOMENTUM L NO-DIM @@ -59,18 +61,20 @@ EV EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV 145.5 0.8 23.0 4. 181.4 0.9 1.9 0.6 ENDDATA 13 -ENDSUBENT 28 -SUBENT 40468003 881020 20050926 0000 -BIB 3 8 -REACTION 1(55-CS-134(N,0),,EN) RESONANCE ENERGY. - 2(55-CS-134(N,TOT),,WID) TOTAL WIDTH OF RESONANCE. - 3(55-CS-134(N,EL),,WID,,2G) 2G*NEUTRON-WIDTH OF RES. -SAMPLE CS-CL POWDER WITH CS-135 CONTENTS-3.0*10**19 - NUCLEI/CM**2, CS-134 CONTENTS-3.0*10**20 NUCLEI/CM**2, - CS-133 CONTENTS-3.52*10**22 NUCLEI/CM**2. -STATUS (DEP,40468004) DATA ARE OBTAINED BY ANALYSING OF DATA - (DEP,40468005) FROM SUBENTS 40468004 AND 40468005 -ENDBIB 8 +ENDSUBENT 31 +SUBENT 40468003 20110816 20111003 20110930 4153 +BIB 3 10 +REACTION 1(55-CS-134(N,0),,EN) Resonance energy. + 2(55-CS-134(N,TOT),,WID) Total width of resonance. + 3(55-CS-134(N,EL),,WID,,2G) 2g*neutron-width of res. +SAMPLE Cs-Cl powder with Cs-135 contents-3.0*10**19 + nuclei/cm**2, Cs-134 contents-3.0*10**20 nuclei/cm**2, + Cs-133 contents-3.52*10**22 nuclei/cm**2. +STATUS (DEP,40468004) Data are obtained by analyzing of data + (DEP,40468005) from SUBENTS 40468004 and 40468005 + (SPSDD,41284007) Superseded by newer publication. + (TABLE) From C,76LOWELL,,1976 +ENDBIB 10 COMMON 1 3 MOMENTUM L NO-DIM @@ -86,13 +90,16 @@ EV EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV 153.5 0.7 9.6 3.9 171. 1.0 10.3 4.2 ENDDATA 8 -ENDSUBENT 25 -SUBENT 40468004 881020 20050926 0000 -BIB 3 3 -REACTION (55-CS-133(N,TOT),,SIG,,RAW) TRANSMISSION -SAMPLE SAMPLE THICKNESS IS 9.514*10*21 NUCLEI/CM**2 -STATUS (APRVD) DATA WERE RECEIVED FROM AUTHOR 770525 -ENDBIB 3 +ENDSUBENT 27 +SUBENT 40468004 20110816 20111003 20110930 4153 +BIB 4 6 +REACTION (55-CS-133(N,TOT),,TRN) Transmission +SAMPLE Sample thickness is 9.514*10*21 nuclei/cm**2 +STATUS (APRVD) Data were received from author 770525 + (TABLE) From author. +HISTORY (19770525R) Data from author. + (20110816A) M.M. SIG,,RAW -> TRN. +ENDBIB 6 NOCOMMON 0 0 DATA 2 3473 EN DATA @@ -3571,13 +3578,18 @@ EV NO-DIM .1639 .7777 .1637 .7696 ENDDATA 3475 -ENDSUBENT 3483 -SUBENT 40468005 881020 20050926 0000 -BIB 3 3 -REACTION (55-CS-134(N,TOT),,SIG,,RAW) TRANSMISSION -SAMPLE SAMPLE IS DESCRIBED IN SUBENT 40468003 -STATUS (APRVD) DATA WERE RECEIVED FROM AUTHOR 770525 -ENDBIB 3 +ENDSUBENT 3486 +SUBENT 40468005 20110816 20111003 20110930 4153 +BIB 4 8 +REACTION (55-CS-134(N,TOT),,TRN) Transmission +SAMPLE Cs-Cl powder with Cs-135 contents-3.0*10**19 + nuclei/cm**2, Cs-134 contents-3.0*10**20 nuclei/cm**2, + Cs-133 contents-3.52*10**22 nuclei/cm**2. +STATUS (APRVD) Data were received from author 1977-05-25 + (TABLE) From author. +HISTORY (19770525R) Data from author. + (20110816A) M.M. SIG,,RAW -> TRN. +ENDBIB 8 NOCOMMON 0 0 DATA 2 2046 EN DATA @@ -5629,5 +5641,5 @@ EV NO-DIM .8267 .4191 .8260 .3933 ENDDATA 2048 -ENDSUBENT 2056 +ENDSUBENT 2061 ENDENTRY 5 diff --git a/exforall/404/40490.x4 b/exforall/404/40490.x4 index 160d8a444..8cef01a4a 100644 --- a/exforall/404/40490.x4 +++ b/exforall/404/40490.x4 @@ -1,61 +1,90 @@ -ENTRY 40490 870410 20050926 0000 -SUBENT 40490001 870410 20050926 0000 -BIB 15 24 -TITLE THERMAL NEUTRON FISSION CROSS-SECTION AND FISSION - RESONANCE INTEGRAL FOR CURIUM-243 -AUTHOR (K.D.ZHURAVLEV,N.I.KROSHKIN) -INSTITUTE (4CCPNIR) -REFERENCE (J,AE,47,(1),55,7907) - (J,AE,39,(4),285,75) EXPERIMENTAL DETALIS -MONITOR (92-U-235(N,F),,SIG) FOR THERMAL NEUTRONS +ENTRY 40490 20110726 20111003 20110930 4153 +SUBENT 40490001 20110726 20111003 20110930 4153 +BIB 17 49 +TITLE Thermal neutron fission cross-section and fission + resonance integral for curium-243 +AUTHOR (K.D.Zhuravlev,N.I.Kroshkin) +INSTITUTE (4RUSNIR) +REFERENCE (J,AE,47,(1),55,197907) + (J,SJA,47,(1),565,1979) English translation of J,AE,47. + #doi:10.1007/BF01133444 +REL-REF (R,,Yu.S.Zamyatnin,R,YK-14,22,1974) Ref. for decay data + (M,40436001,K.D.Zhuravlev+,R,YK-19,3,1975) + Details of method. + (M,40436001,K.D.Zhuravlev+,J,AE,39,(4),285,1975) + Details of method. + (M,40436001,K.D.Zhuravlev+,J,SJA,39,907,1975) + English translation of J,AE,39 . +MONITOR (92-U-235(N,F),,SIG) For thermal neutrons (92-U-235(N,F),,RI) -SAMPLE CURIUM-242 CONTENT IS 0.15+-0.07 PERCENT - CURIUM-243 37.29+-1.34 - CURIUM-244 61.61+-1.34 - CURIUM-245 0.94+-0.10 -METHOD METHOD OF CADMIUM RATIO -INC-SOURCE (REAC) REACTOR 'CM-2' -FACILITY (REAC) REACTOR 'CM-2' +MONIT-REF (,,R,BNL-325,1,1973) +SAMPLE Curium-242 content is 0.15+-0.07 % + Curium-243 37.29+-1.34 % + Curium-244 61.61+-1.34 % + Curium-245 0.94+-0.10 % + On Al backing of 0.1 mm thickness. + U, Cm samples of about 10 mm diameter. + Number of nuclei in sample was defined by spontaneous + fission number of Cm-244 and Cm-242. +METHOD Method of cadmium ratio + Cd ratio for U-235 for 1 mm thickness Cd filtered beam + was 40. +DECAY-DATA (96-CM-244,1.270E+7YR,SF) (1.270+-0.007)E+7YR + (96-CM-242,6.09E+6YR,SF) (6.09+-0.18)E+6YR + Half-lives for spontaneous fission from REL-REF of + Yu.S.Zamyatnin. +INC-SOURCE (REAC) Reactor 'CM-2' +FACILITY (REAC) Reactor 'CM-2' PART-DET (N) -DETECTOR NO INFORMATION -CORRECTION INTRODUCED ON CM-244 AND CM-245 FISSION -HALF-LIFE (HL1,96-CM-244) FOR FISSION - (HL2,96-CM-245) FOR FISSION -ERR-ANALYS (DATA-ERR) NOT SPECIFIED -HISTORY (800807C) COMPILED AT THE CJD - (870410U) REACTION CODE IN SAN 002 CORRECTED AND - EN-MIN IN SAN 003 INTRODUCED -ENDBIB 24 -COMMON 8 6 -MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR HL1 HL1-ERR -HL2 HL2-ERR -B B B B YR YR -YR YR - 582.2 1.3 275. 5. 1.270E+7 .007E+7 - 6.09E+6 0.18E+6 -ENDCOMMON 6 -ENDSUBENT 34 -SUBENT 40490002 870410 20050926 0000 -BIB 2 2 +DETECTOR (FISCH) +CORRECTION Introduced on Cm-244 and Cm-245 fission. + For the fact, that U c-s do not follow the 1/SQRT(E) + low - 0.965. + For Cm - it was supposed that c-s follows 1/sqrt(E) + low. +ERR-ANALYS (DATA-ERR) Not specified +HISTORY (19800807C) Compiled at the CJD + (19870410U) REACTION code in SAN 002 corrected and + EN-MIN in SAN 003 introduced + (20110726A) Upper -> lower case correction. + Reference of Engl.translation was added. + BIB information was added. + Dates were corrected for 4-digits year. +ENDBIB 49 +COMMON 4 3 +MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR +B B B B + 582.2 1.3 275. 5. +ENDCOMMON 3 +ENDSUBENT 56 +SUBENT 40490002 20110726 20111003 20110930 4153 +BIB 4 7 REACTION (96-CM-243(N,F),,SIG,,MXW) -INC-SPECT THERMAL NEUTRONS -ENDBIB 2 +INC-SPECT Thermal neutrons . + Temperature of Maxwellian neutron spectrum at reactor + output was 353 K. +REL-REF (A,10681001,C.E.Bemis+,J,NSE,63,413,197708) + Agree with value of C.E.Bemis+ 609.6+-25.9 B. +STATUS (TABLE) Table of J,AE,47,(1),55,1979. +ENDBIB 7 NOCOMMON 0 0 DATA 3 1 EN-DUMMY DATA DATA-ERR EV B B 2.5300E-02 672. 60. ENDDATA 3 -ENDSUBENT 10 -SUBENT 40490003 870410 20050926 0000 -BIB 1 1 +ENDSUBENT 15 +SUBENT 40490003 20110726 20111003 20110930 4153 +BIB 3 3 REACTION (96-CM-243(N,F),,RI) -ENDBIB 1 +REL-REF (A,10681005,C.E.Bemis+,J,NSE,63,413,197708) +STATUS (TABLE) Table of J,AE,47,(1),55,1979. +ENDBIB 3 NOCOMMON 0 0 DATA 3 1 EN-MIN DATA DATA-ERR EV B B 0.68 1480. 150. ENDDATA 3 -ENDSUBENT 9 +ENDSUBENT 11 ENDENTRY 3 diff --git a/exforall/405/40501.x4 b/exforall/405/40501.x4 index a608f7788..514f20935 100644 --- a/exforall/405/40501.x4 +++ b/exforall/405/40501.x4 @@ -1,80 +1,88 @@ -ENTRY 40501 910128 20050926 0000 -SUBENT 40501001 910128 20050926 0000 -BIB 16 62 -TITLE MEASUREMENT OF FISSION CROSS-SECTION RATIO - FOR PU-239 AND U-235 IN NEUTRON ENERGY RANGE - 0.024-7.4 MEV -AUTHOR (B.I.FURSOV.V.M.KUPRIYANOV.V.I.IVANOV.G.N.SMIRENKIN) -INSTITUTE (4CCPFEI) -REFERENCE (C,75KIEV,6,3,7506) DATA AND GRAPH GIVEN - (C,77KIEV,3,144,7704) GRAPH GIVEN - (J,AE,43,(4),261,7710) DATA AND GRAPH GIVEN - (P,YFI-25,3,7712) +ENTRY 40501 20110711 20111003 20110930 4153 +SUBENT 40501001 20110711 20111003 20110930 4153 +BIB 16 69 +TITLE Measurement of the ratio of Pu-239 and U-235 fission + cross-section for 0.024-7.4 MeV neutrons. +AUTHOR (B.I.Fursov,V.M.Kupriyanov,V.I.Ivanov,G.N.Smirenkin) +INSTITUTE (4RUSFEI) +REFERENCE (J,AE,43,(4),261,197710) Data and graph given + (J,SJA,43,(4),894,1977) + #doi:10.1007/BF01117993 + (C,75KIEV,6,3,197506) Data and graph given + (C,77KIEV,3,144,197704) Graph given + (P,YFI-25,3,197712) MONITOR (92-U-235(N,F),,SIG) -METHOD DIRECT REGISTRATION THE FISSION FRAGMENTS - BY MEANS OF DOUBLE IONIZATION CHAMBER AND GLASS - DETECTORS -PART-DET (FF) FISSION FRAGMENTS -DETECTOR DOUBLE FISSION IONIZATION CHAMBER AND GLASS DETECTOR -FACILITY (VDG) VAN-DE-GRAAFF -INC-SOURCE (P-LI7) PROTON-TRITIUM AND PROTON-LITHIUM REACTIONS - (P-T) FOR NEUTRON ENERGY RANGE 0.024-0.320 MEV - WERE USED. - (D-D) DEUTERON-DEITERIUM REACTION FOR NEUTRON ENERGY - RANGE 0.320-7.4 MEV WAS USED. -SAMPLE PU-239 TARGET CONTAINES 99.891 PER-CENT OF PU-239, - 0.109 PER-CENT OF PU-240. - U-235 TARGET CONTAINS 99.9955 PER-CENT OF U-235, - 0.0010 PER-CENT OF U-234,0.0035 PER-CENT OF U-236 - AND LESS 0.0005 PER-CENT OF U-238. - IN MEASUREMENTS BY MEANS OF GLASS DETECTORS - U-235 TARGET CONTAINS 91.2326 PER-CENT OF U-235, - 1.1003 PER-CENT OF U-234,0.0036 PER-CENT OF U-236, - 7.6635 PER-CENT OF U-238. -CORRECTION IN MEASUREMENTS WITH GLASS DETECTORS FOLLOWING - CORRECTIONS WERE INTRODUCED - 1.DIFFERENCE OF NEUTRON FLUX IN PU-239,U-235 TARGETS, - 2.CORRECTION ON ANGULAR DISTRIBUTION OF FISSION - FRAGMENTS, - 3.CORRECTION FOR FISSION OF DIFFERENT ISOTOPES, - 4.BACKGROUND OF NEUTRONS OF EXPERIMENTAL ROOM AND - SCATTERING ON TARGET CONSTRUCTION, - 5.BACKGROUND OF NEUTRONS ASSOCIATING (P-N) REACTION. -ERR-ANALYS IN DATA TABLES A TOTAL ERROR IS REPRESENTED AND - IT IS DETERMINED BY MEAN-SQUARE ERROR,CONSISTING - OF FOLLOWING VALUES - 1.ERROR THE ENERGETIC DEPENDENCE OF FISSION CROSS - SECTION RATIO FOR PU-239 AND U-235 (0.5-1.5 PER-CENT) - 2.AVERAGE ERROR OF ABSOLUTE VALUE,OBTAINED BY GLASS - METHOD (1.3 PER-CENT), - 3.ERROR OF NORMALIZATION ON ABSOLUTE VALUES OF FISSION - CROSS-SECTION RATIO (0.22 PER-CENT), - 4.ERROR AT THE FISSION THE OTHER ISOTORES (0.1PER-CENT) - 5.ERROR OF BACKGROUND THE ASSOCIATING (D-N) REACTIONS - (0.54 PER-CENT), - 6.ERROR OF REGISTRATION EFFICIENCY BY FISSION CHAMBER - (0.3 PER-CENT). -ANALYSIS CALIBRATION OF ENERGETIC DEPENDENCE THE FISSION CROSS - SECTION RATIO BY MEANS OF GLASS METHOD WAS MADE. - QUANTITY OF FISSIBLE NUCLEI WAS DEFINED BY TWO METHODS - NAMELY BY MEANS OF ALPHA-ACTIVITY OF TARGETS AND - BY MEASUREMENTS IN THERMAL COLUMN OF REACTOR. -STATUS FROM PUBLISHED SOURCES LISTED UNDER 'REFERENCE' -HISTORY (771226C) COMPILED AT THE CENTRE - CJD - (910128A) DATA SUPERCEEDED ON THE REASON OF DATA REPE- - TITION IN ENTRY 40024 -ENDBIB 62 +METHOD Direct registration the fission fragments + by means of double ionization chamber and glass + detectors +PART-DET (FF) Fission fragments +DETECTOR (FISCH) Double fission ionization chamber and glass + (GLASD) detector +FACILITY (VDG) Van-de-Graaff +INC-SOURCE (P-LI7) Proton-tritium and proton-lithium reactions + (P-T) for neutron energy range 0.024-0.320 MeV + were used. + (D-D) Deuteron-deuterium reaction for neutron energy + range 0.320-7.4 MeV was used. +SAMPLE Pu-239 target contains 99.891 % of Pu-239, + 0.109 % of Pu-240. + U-235 target contains 99.9955 % of U-235, + 0.0010 % of U-234, 0.0035 % of U-236 + and less 0.0005 % of U-238. + In measurements by means of glass detectors: + U-235 target contains 91.2326 % of U-235, + 1.1003 % of U-234, 0.0036 % of U-236, + 7.6635 % of U-238. +CORRECTION In measurements with glass detectors following + corrections were introduced: + 1.DIfference of neutron flux in Pu-239,U-235 targets, + 2.Correction on angular distribution of fission + fragments, + 3.Correction for fission of different isotopes, + 4.Background of neutrons of experimental room and + scattering on target construction, + 5.Background of neutrons associating (P-N) reaction. +ERR-ANALYS In DATA tables a total error is represented and + it is determined by mean-square error,consisting + of following values: + 1.Error the energetic dependence of fission cross + section ratio for Pu-239 and U-235 (0.5-1.5 %). + 2.Average error of absolute value,obtained by glass + method (1.3 %). + 3.Error of normalization on absolute values of fission + cross-section ratio (0.22 %). + 4.Error at the fission the other isotopes (0.1%). + 5.Error of background the associating (d-n) reactions + (0.54 %). + 6.Error of registration efficiency by fission chamber + (0.3 %). + Detailed error analysis is in ENTRY 40824. +ANALYSIS Calibration of energetic dependence the fission cross + section ratio by means of glass method was made. + Quantity of fissile nuclei was defined by two methods + namely by means of alpha-activity of targets and + by measurements in thermal column of reactor. +STATUS (TABLE) From published sources listed under 'REFERENCE' + (SPSDD,40824001) Superseded by ENTRY 40824. +HISTORY (19771226C) Compiled at the centre - CJD + (19910128A) Data superseded on the reason of data + repetition in ENTRY 40824 + (20110711A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + Ref. J,SJA was added. BIB information was added. +ENDBIB 69 NOCOMMON 0 0 -ENDSUBENT 65 -SUBENT 40501002 910128 20050926 0000 -BIB 3 5 +ENDSUBENT 72 +SUBENT 40501002 20110711 20111003 20110930 4153 +BIB 3 6 REACTION ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) -FLAG (1.) DATA OBTAINED WITH HELP OF GLASS DETECTOR. - ALL OTHER DATA OBTAINED WITH HELP THE IONIZATION - CHAMBER. -STATUS (SPSDD) DATA SUPERCEEDED -ENDBIB 5 +FLAG (1.) Data obtained with help of glass detector. + All other data obtained with help the ionization + chamber. +STATUS (SPSDD,40824002) Data superseded + (SPSDD,40824003) +ENDBIB 6 NOCOMMON 0 0 NODATA 0 0 -ENDSUBENT 9 +ENDSUBENT 10 ENDENTRY 2 diff --git a/exforall/405/40506.x4 b/exforall/405/40506.x4 index 2e323fd16..f9a09a37d 100644 --- a/exforall/405/40506.x4 +++ b/exforall/405/40506.x4 @@ -1,45 +1,58 @@ -ENTRY 40506 20060905 20070521 20060816 4139 -SUBENT 40506001 20060905 20070521 20060816 4139 -BIB 16 48 -TITLE RATIO FISSION CROSS-SECTION MEASUREMENT FOR U-238 - AND U-235 IN NEUTRON ENERGY RANGE 1-7 MEV -AUTHOR (B.I.FURSOV,V.H.KUPRIYANOV,B.K.MASLENNIKOV, - G.N.SMIRENKIN) +ENTRY 40506 20110708 20111003 20110930 4153 +SUBENT 40506001 20110708 20111003 20110930 4153 +BIB 16 63 +TITLE Measurement of the ratio of the U-238 and U-235 cross + sections for fission by 1-7-MeV neutrons +AUTHOR (B.I.Fursov,V.H.Kupriyanov,B.K.Maslennikov, + G.N.Smirenkin) INSTITUTE (4RUSFEI) REFERENCE (J,AE,43,(3),181,197709) Data And Graphs Given (C,77KIEV,3,144,197704) Graphs Only -STATUS These Data Replace The Data Of Entry 40345 -MONITOR (92-U-235(N,F),,SIG) -METHOD Direct Registration The Fission Fragments - By Means Of Double Fission Ionization Chamber -PART-DET (FF) Fission Fragments -DETECTOR (FISCH) Two Double Fission Ionization Chambers Filled - By Argon (90 Per-cents) And CO2 (10 Per-cents) + (J,SJA,43,(3),808,1977) Engl.transl. of J,AE. + #doi:10.1007/BF01119041 +STATUS (TABLE) Table 1 of J,AE,43,(3),181,1977 + These data replace the data of Entry 40345 +MONITOR (92-U-235(N,F),,SIG) At 1.5, 2.0, 2.5, 3.0 MeV. +METHOD Direct registration the fission fragments + by means of double fission ionization chamber +PART-DET (FF) Fission fragments +DETECTOR (FISCH) Two double fission ionization chambers filled + by argon (90 per-cents) and co2 (10 per-cents) FACILITY (VDG) Van-De-Graaff -INC-SOURCE (P-LI7) Proton-Lithium And Proton-tritium Reactions - (P-T) For Neutron Energy Range 1-3 Mev Were Used. - (D-D) Deuteron-Deuterium Reaction For Neutron Energy - Range 3.6-7 Mev Was Used. -SAMPLE Layers Of 0.3-0.4 mg/cm2 Thickness, Isotopical Purity: +INC-SOURCE (P-LI7) Proton-lithium and proton-tritium reactions + (P-T) For neutron energy range 1-3 Mev was used. + (D-D) Deuteron-deuterium reaction for neutron energy + range 3.6-7 Mev was used. +SAMPLE Layers of 0.3-0.4 mg/cm2 thickness, isotopical purity: U-235 - 99.99%, U-238 - 99.6%. -CORRECTION In Results Of Measurements The Following Corrections - Were Introduced 1.Fission Of Other Isotopes By Fast - Neutrons,2.Energetic Dependence Of Efficiency - Of Fission Fragment Registration,3.Background Of - Neutrons Scattering On Target Construction,4.Neutron - Background Of Experimental Room,5.Background Of - Neutrons Of Associating (P-N) Reaction,6.Difference - Of Neutron Flux In U-235 And U-238 Targets. -ERR-ANALYS (ERR-T) Total Error Of Measurements Includes Errors: - 1.Statistical Error, - 2.Error From Fission Of Other Isotopes, - 3.Error From Fission By Neutrons Scattering On Target - Construction, - (ERR-1) 4.Error Of Energy Dependence Of Efficiency Of - Fission Fragment Registration (0.5-4.8%), Maximal - (ERR-2) 5.Error of normalization (0.1-0.3%), Maximal - .All These Errors Depend On Neutron Energy And - For Each Neutron Energy Independently Were Found. +CORRECTION In results of measurements the following corrections + were introduced 1.Fission of other isotopes by fast + neutrons 1.01; 2.EnergY dependence of efficiency + of fission fragment registration-1.48; 3.Background of + neutrons scattering on target construction-2.10; + 4.Neutron background of experimental room- 0.28; + 5.Neutron background of associated P-N reaction-0.58, + 6.Difference of neutron flux in U-235 and U-238 + targets - 1.61. +ERR-ANALYS (ERR-T) Total error of measurements includes errors: + (ERR-SYS) Systematical error -0.55. + (ERR-S,0.3,2.) Statistical error + (ERR-1,0.54,3.2) Error of energy dependence of + efficiency of fission fragment registration + (ERR-2) Error of normalization + (ERR-3) Average error of monitor values. + (ERR-4,0.1,3.) Error from fission of other isotopes, + (ERR-5) Error of background of exp hall , + (ERR-6) Error from fission by neutrons scattering on + target ; + (ERR-7,,0.4)Error of contribution of p,n reaction at + 3.7 MeV, + (ERR-8,,2.8)Error of contribution of d,n reaction, + 3.7 MeV, + (ERR-9) Error of energy dependence of FF registration + efficiency. + .All these errors depend on neutron energy and + for each neutron energy independently were found. ANALYSIS Fission Cross-section Ratio Is Normalized At Neutron Energy En =1.5,2.0, 2.5, 3.0 Mev To Absolute Sigma Fission Ratio Which Obtained By Four Independent @@ -49,13 +62,15 @@ HISTORY (19771226C) Compiled At The Centre DATA-ERR To ERR-T Changed And Obsolete Keywords Modified (20060905A) M.M. Misprint in data was corrected. -ENDBIB 48 -COMMON 2 3 -ERR-1 ERR-2 -PER-CENT PER-CENT -4.8 0.3 + (20110709U) M.M. Ref. J,SJA was added. + ERR-ANALYS was corrected according to now-days rules. +ENDBIB 63 +COMMON 5 3 +ERR-2 ERR-3 ERR-5 ERR-6 ERR-9 +PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT + 0.1 0.54 0.14 0.23 0.3 ENDCOMMON 3 -ENDSUBENT 55 +ENDSUBENT 70 SUBENT 40506002 20060905 20070521 20060816 4139 BIB 1 1 REACTION ((92-U-238(N,F),,SIG)/(92-U-235(N,F),,SIG)) diff --git a/exforall/405/40510.x4 b/exforall/405/40510.x4 index 47d23bf95..ed07f43e4 100644 --- a/exforall/405/40510.x4 +++ b/exforall/405/40510.x4 @@ -1,13 +1,13 @@ -ENTRY 40510 20110426 20110624 20110623 4152 -SUBENT 40510001 20110426 20110624 20110623 4152 -BIB 13 38 -TITLE Determination of the resonance structure characte- - ristics of the total cross-section and fission - cross-section for U-235 and Pu-239 in the neutron - energy range 2 eV - 20 keV +ENTRY 40510 20110706 20111003 20110930 4153 +SUBENT 40510001 20110706 20111003 20110930 4153 +BIB 13 39 +TITLE Determination of the details of the resonance structure + of both the total cross section and the fission cross + section of U-235 and Pu-239 for 2 eV-20-keV neutrons. INSTITUTE (4ZZZDUB,4RUSFEI) REFERENCE (J,AE,48,(6),377,198006) - (J,AE/T,48,(6),381,1980) Engl.translation of J,AE,48 + (J,SJA,48,(6),381,1980) Engl.translation of J,AE,48 + #doi:10.1007/BF01126262 (C,80KIEV,2,290,198009) Pu-239 res.parameters. (T,GRIGORIEV,2005) U-235 c-s are confirmed, Pu-239 c-s are used for comparison. @@ -39,9 +39,10 @@ HISTORY (19810421C) Compiled at the CJD References T,GRIGORIEV,2005, J,YK,1980,(2) and J,AE/T were added. BIB information was added. -ENDBIB 38 + (20110706A) M.M. AE/T -> SJA +ENDBIB 39 NOCOMMON 0 0 -ENDSUBENT 41 +ENDSUBENT 42 SUBENT 40510002 20110426 20110624 20110623 4152 BIB 6 11 REACTION 1(94-PU-239(N,0),,EN,,AA) diff --git a/exforall/405/40568.x4 b/exforall/405/40568.x4 index b38613d77..595e5aaf0 100644 --- a/exforall/405/40568.x4 +++ b/exforall/405/40568.x4 @@ -1,46 +1,75 @@ -ENTRY 40568 860417 20050926 0000 -SUBENT 40568001 860417 20050926 0000 -BIB 13 25 -INSTITUTE (4CCPFEI) -REFERENCE (C,77KIEV,2,27,7704) - (R,YFI-25,18,7712) - (J,AE,43,(3),176,7709) -AUTHOR (N.S.BIRJUKOV,B.V.ZHURAVLJOV,N.V.KORNILOV,V.I.POPOV, - A.P.RUDENKO,O.A.SAL'NIKOV,V.I.TRYKOVA) -TITLE SCATTERING OF 9.1+-0.2MEV NEUTRONS BY LI-7 NUCLEI -FACILITY (CYCLO) CYCLOTRON FEI 150.CM -INC-SOURCE (P-T) -SAMPLE METAL LITHIUM IN FORM OF CYLINDER (DIAMETER IS 50.MM, - HEIGHT IS 68.MM) -METHOD (TOF) FLIGHT BASE IS 201.CM -DETECTOR (SOLST) DETECTOR WITH STILBENE CRYSTAL -MONITOR SCATTERING CROSS-SECTION OF HYDROGEN +ENTRY 40568 20110707 20111003 20110930 4153 +SUBENT 40568001 20110707 20111003 20110930 4153 +BIB 15 47 +INSTITUTE (4RUSFEI) +REFERENCE (C,77KIEV,2,27,197704) Data of Subents 007-013 + (R,YFI-25,18,197712) All data. + (J,AE,43,(3),176,197709) Data of Subents 007-013 + (J,SJA,43,(3),804,1977) Engl. transl. of J,AE . + #doi:10.1007/BF01119040 +AUTHOR (N.S.Biryukov,B.V.Zhuravljov,N.V.Kornilov,V.I.Popov, + A.P.Rudenko,O.A.Sal'nikov,V.I.Trykova) +TITLE Scattering of 9.1+-0.2MeV neutrons by Li-7 nuclei +FACILITY (CYCLO,4RUSFEI) Cyclotron FEI 150-cm . +REL-REF (I,,N.S.Biryukov+,P,FEI-687,1976) Exp. facility,method. + (R,,V.I.Ashby+,J,PR,129,(4),1771,1963) + Ref. for ASSUM data. +INC-SOURCE (P-T) Gas T target. +SAMPLE Metal lithium in form of cylinder (diameter is 50.mm, + height is 68.mm) +METHOD (TOF) Flight base is 201.cm +DETECTOR (SOLST) Detector with stilbene crystal of 70 mm + diameter, 68 mm heigh and FEU-30. + Detector efficiency was defined by Cf-252 prompt + neutron fission spectum measured by calibrated + detector. Resolution 1.4 nsec/m. +MONITOR (1-H-1(N,EL)1-H-1,,SIG) Scattering c-s of hydrogen + in form of polyethylene sample of 15 mm diameter 60 mm + height. +CORRECTION For beam attenuation and multiple scattering in sample + was calculated by Monte-Carlo method - from 5 to 8%. STATUS (APRVD) -HISTORY (790514C) - (850927U) -ERR-ANALYS (ERR-T) TOTAL ERROR - STATISTICAL -10.PERCENT FOR 1.MEV AND 20.PERCENT FOR - 7.MEV - MONITORING - 3.PERCENT - EFFICIFNCY - 5.PERCENT - INACCURACY OF METHOD- 3.PERCENT FOR 1.MEV AND - 9.PERCENT FOR 7.MEV - NORMALIZATION - 7.PERCENT -ENDBIB 25 -COMMON 2 3 -EN EN-ERR -MEV MEV - 9.1000E+00 2.0000E-01 +ERR-ANALYS (ERR-T) Total error + (ERR-S,10.,20.) Statistical-10.% for 1.MeV and 20.% FOR + 7.MeV. + (ERR-1) Uncertainty of monitoring - 3.% + (ERR-2) Uncertainty of detector efficiency - 5.% + (ERR-3,3.,9.) Uncertainty due to time-of-flight- + 3.% for 1.MeV 9.% for 7.MeV + (ERR-4) Uncertainty of TOF distance. + (ERR-5) Uncertainty of normalization - 7.% +HISTORY (19790514C) + (19850927U) + (20110707A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + BIB information was added. + Ref. J,SJA was added. + Subent 013 was added. + In REACTION of Subents 002-006: + "INL)3-LI-7," -> "X)0-NN-1," according to the comment + of N.Otsuka (NDS IAEA). +ENDBIB 47 +COMMON 4 3 +EN EN-ERR ERR-4 ERR-5 +MEV MEV PER-CENT PER-CENT + 9.1 0.2 1. 7. ENDCOMMON 3 -ENDSUBENT 32 -SUBENT 40568002 850927 20050926 0000 -BIB 1 1 -REACTION (3-LI-7(N,INL)3-LI-7,,DA/DE) -ENDBIB 1 -COMMON 1 3 -ANG -ADEG - 3.0000E+01 +ENDSUBENT 54 +SUBENT 40568002 20110707 20111003 20110930 4153 +BIB 4 8 +REACTION (3-LI-7(N,X)0-NN-1,,DA/DE) +ERR-ANALYS (ERR-6) Uncertainty of separation of different groups + of neutrons +STATUS (TABLE) Table 3 of R,YFI-25,18,1977 +COMMENT Of compiler M.M. EN in DATA block was rouned to one + meaning digit after point (e.g. 0.596 -> 0.6, + 0.696 -> 0.7, 1.002 -> 1.0 and so on) . + Because Entry was approved at 1979, so not corrected. +ENDBIB 8 +COMMON 2 3 +ANG ERR-6 +ADEG PER-CENT + 3.0000E+01 10. ENDCOMMON 3 DATA 3 51 E DATA ERR-T @@ -97,11 +126,16 @@ MEV MB/SR/MEV MB/SR/MEV 6.0400E+00 1.4700E+00 1.4100E+00 6.2300E+00 5.9000E-01 5.9000E-01 ENDDATA 53 -ENDSUBENT 63 -SUBENT 40568003 850927 20050926 0000 -BIB 1 1 -REACTION (3-LI-7(N,INL)3-LI-7,,DA/DE) -ENDBIB 1 +ENDSUBENT 70 +SUBENT 40568003 20110707 20111003 20110930 4153 +BIB 3 6 +REACTION (3-LI-7(N,X)0-NN-1,,DA/DE) +STATUS (TABLE) Table 3 of R,YFI-25,18,1977 +COMMENT Of compiler M.M. EN in DATA block was rouned to one + meaning digit after point (e.g. 0.596 -> 0.6, + 0.696 -> 0.7, 1.002 -> 1.0 and so on) . + Because Entry was approved at 1979, so not corrected. +ENDBIB 6 COMMON 1 3 ANG ADEG @@ -156,11 +190,17 @@ MEV MB/SR/MEV MB/SR/MEV 4.9200E+00 4.4000E-01 4.4000E-01 5.0600E+00 2.2000E-01 2.2000E-01 ENDDATA 47 -ENDSUBENT 57 -SUBENT 40568004 850927 20050926 0000 -BIB 1 1 -REACTION (3-LI-7(N,INL)3-LI-7,,DA/DE) -ENDBIB 1 +ENDSUBENT 62 +SUBENT 40568004 20110707 20111003 20110930 4153 +BIB 3 7 +REACTION (3-LI-7(N,X)0-NN-1,,DA/DE) +STATUS (TABLE) Table 3 of R,YFI-25,18,1977 + Data are presented on Fig. of C,77KIEV,2,27,1977. +COMMENT Of compiler M.M. EN in DATA block was rouned to one + meaning digit after point (e.g. 0.596 -> 0.6, + 0.696 -> 0.7, 1.002 -> 1.0 and so on) . + Because Entry was approved at 1979, so not corrected. +ENDBIB 7 COMMON 1 3 ANG ADEG @@ -207,11 +247,16 @@ MEV MB/SR/MEV MB/SR/MEV 3.9800E+00 5.0000E-01 5.0000E-01 4.0800E+00 2.5000E-01 2.5000E-01 ENDDATA 39 -ENDSUBENT 49 -SUBENT 40568005 850927 20050926 0000 -BIB 1 1 -REACTION (3-LI-7(N,INL)3-LI-7,,DA/DE) -ENDBIB 1 +ENDSUBENT 55 +SUBENT 40568005 20110707 20111003 20110930 4153 +BIB 3 6 +REACTION (3-LI-7(N,X)0-NN-1,,DA/DE) +STATUS (TABLE) Table 3 of R,YFI-25,18,1977 +COMMENT Of compiler M.M. EN in DATA block was rouned to one + meaning digit after point (e.g. 0.596 -> 0.6, + 0.696 -> 0.7, 1.002 -> 1.0 and so on) . + Because Entry was approved at 1979, so not corrected. +ENDBIB 6 COMMON 1 3 ANG ADEG @@ -253,15 +298,22 @@ MEV MB/SR/MEV MB/SR/MEV 3.5200E+00 9.9000E-01 7.4000E-01 3.6100E+00 4.7000E-01 4.7000E-01 ENDDATA 34 -ENDSUBENT 44 -SUBENT 40568006 850927 20050926 0000 -BIB 1 1 -REACTION (3-LI-7(N,INL)3-LI-7,,DA/DE) -ENDBIB 1 -COMMON 1 3 -ANG -ADEG - 1.5000E+02 +ENDSUBENT 49 +SUBENT 40568006 20110707 20111003 20110930 4153 +BIB 4 8 +REACTION (3-LI-7(N,X)0-NN-1,,DA/DE) +ERR-ANALYS (ERR-6) Uncertainty of separation of different groups + of neutrons +STATUS (TABLE) Table 3 of R,YFI-25,18,1977 +COMMENT Of compiler M.M. EN in DATA block was rouned to one + meaning digit after point (e.g. 0.596 -> 0.6, + 0.696 -> 0.7, 1.002 -> 1.0 and so on) . + Because Entry was approved at 1979, so not corrected. +ENDBIB 8 +COMMON 2 3 +ANG ERR-6 +ADEG PER-CENT + 1.5000E+02 4. ENDCOMMON 3 DATA 3 28 E DATA ERR-T @@ -295,14 +347,22 @@ MEV MB/SR/MEV MB/SR/MEV 3.1100E+00 1.6000E+00 1.0900E+00 3.2100E+00 5.9000E-01 5.9000E-01 ENDDATA 30 -ENDSUBENT 40 -SUBENT 40568007 850927 20050926 0000 -BIB 1 3 -REACTION (3-LI-7(N,EL)3-LI-7,,DA) ELASTIC SCATTERING CROSS- - SECTION PLUS INELASTIC SCATTERING COMPONENT ON 0.478 - MEV STATE -ENDBIB 3 -NOCOMMON 0 0 +ENDSUBENT 47 +SUBENT 40568007 20110707 20111003 20110930 4153 +BIB 3 7 +REACTION (3-LI-7(N,SCT)3-LI-7,PAR,DA) + Elastic scattering cross-section plus inelastic + scattering component on 0.478 MeV state +STATUS (TABLE) Table of C,77KIEV,2,27,1977. +HISTORY (20110707A) REACTION was corrected: + 3-LI-7(N,EL)3-LI-7,,DA) -> + (3-LI-7(N,SCT)3-LI-7,PAR,DA) +ENDBIB 7 +COMMON 2 3 +E-LVL E-LVL +MEV MEV + 0.478 0. +ENDCOMMON 3 DATA 3 5 ANG DATA ERR-T ADEG MB/SR MB/SR @@ -312,11 +372,12 @@ ADEG MB/SR MB/SR 1.2000E+02 3.7600E+01 3.5000E+00 1.5000E+02 2.8200E+01 2.8000E+00 ENDDATA 7 -ENDSUBENT 15 -SUBENT 40568008 860417 20050926 0000 -BIB 1 1 +ENDSUBENT 23 +SUBENT 40568008 20110707 20111003 20110930 4153 +BIB 2 2 REACTION (3-LI-7(N,X)0-NN-1,PAR,DA) -ENDBIB 1 +STATUS (TABLE) Table of C,77KIEV,2,27,1977. +ENDBIB 2 COMMON 1 3 E-MIN MEV @@ -331,11 +392,12 @@ ADEG MB/SR MB/SR 1.2000E+02 2.3700E+01 2.2000E+00 1.5000E+02 2.6200E+01 2.6000E+00 ENDDATA 7 -ENDSUBENT 17 -SUBENT 40568009 860417 20050926 0000 -BIB 1 1 +ENDSUBENT 18 +SUBENT 40568009 20110707 20111003 20110930 4153 +BIB 2 2 REACTION (3-LI-7(N,INL)3-LI-7,PAR,DA) -ENDBIB 1 +STATUS (TABLE) Table of C,77KIEV,2,27,1977. +ENDBIB 2 COMMON 1 3 E-LVL MEV @@ -350,24 +412,42 @@ ADEG MB/SR MB/SR 1.2000E+02 3.5000E+00 4.0000E-01 1.5000E+02 2.2000E+00 3.0000E-01 ENDDATA 7 -ENDSUBENT 17 -SUBENT 40568010 850927 20050926 0000 -BIB 1 3 -REACTION (3-LI-7(N,EL)3-LI-7,,SIG) ELASTIC SCATTERING CROSS- - SECTION PLUS INELASTIC SCATTERING COMPONENT ON 0.478 - MEV STATE -ENDBIB 3 -NOCOMMON 0 0 +ENDSUBENT 18 +SUBENT 40568010 20110707 20111003 20110930 4153 +BIB 5 13 +REACTION (3-LI-7(N,SCT)3-LI-7,PAR,SIG) + Elastic scattering cross-section plus inelastic + scattering component on 0.478 MeV state +ANALYSIS (INTAD) Integration over angle the DA approximated by + Legendre polynomials. +COMMENT Of compiler M.M. + In Table of C,77KIEV,2,27,1977 there is misprint for + these data: 277. -> 1277. +STATUS (TABLE) Text, page 30, of C,77KIEV,2,27,1977. + (DEP,40568007) See ANALYSIS. +HISTORY (20110707A) REACTION was corrected: + 3-LI-7(N,EL)3-LI-7,,SIG) -> + (3-LI-7(N,SCT)3-LI-7,PAR,SIG) +ENDBIB 13 +COMMON 2 3 +E-LVL E-LVL +MEV MEV +0.478 0. +ENDCOMMON 3 DATA 2 1 DATA ERR-T MB MB 1.2770E+03 1.3300E+02 ENDDATA 3 -ENDSUBENT 11 -SUBENT 40568011 860417 20050926 0000 -BIB 1 1 +ENDSUBENT 25 +SUBENT 40568011 20110707 20111003 20110930 4153 +BIB 3 5 REACTION (3-LI-7(N,X)0-NN-1,PAR,SIG) -ENDBIB 1 +ANALYSIS (INTAD) Integration over angle the DA approximated by + Legendre polynomials. +STATUS (TABLE) Table of C,77KIEV,2,27,1977. + (DEP,40568008) +ENDBIB 5 COMMON 1 3 E-MIN MEV @@ -378,11 +458,15 @@ DATA ERR-T MB MB 5.1800E+02 3.7000E+01 ENDDATA 3 -ENDSUBENT 13 -SUBENT 40568012 860417 20050926 0000 -BIB 1 1 +ENDSUBENT 17 +SUBENT 40568012 20110707 20111003 20110930 4153 +BIB 3 5 REACTION (3-LI-7(N,INL)3-LI-7,PAR,SIG) -ENDBIB 1 +ANALYSIS (INTAD) Integration over angle the DA approximated by + Legendre polynomials. +STATUS (TABLE) Table of C,77KIEV,2,27,1977. + (DEP,40568009) See ANALYSIS. +ENDBIB 5 COMMON 1 3 E-LVL MEV @@ -393,5 +477,24 @@ DATA ERR-T MB MB 1.1600E+02 1.1000E+01 ENDDATA 3 -ENDSUBENT 13 -ENDENTRY 12 +ENDSUBENT 17 +SUBENT 40568013 20110707 20111003 20110930 4153 +BIB 4 9 +REACTION (3-LI-7(N,TOT),,SIG,,,DERIV) +ANALYSIS Defined as sum of C-S of Subents 10,11, and n,2n c-s: + 1277+517+5=1799 . +ASSUMED (ASSUM,3-LI-7(N,2N)3-LI-6,,SIG) + Used to take into account the contribution of n,2n + reaction. +STATUS (TABLE) Table of C,77KIEV,2,27,1977. + (DEP,40568010) See ANALYSIS. + (DEP,40568011) +ENDBIB 9 +NOCOMMON 0 0 +DATA 3 1 +DATA ERR-T ASSUM +MB MB MB + 1799. 173. 5. +ENDDATA 3 +ENDSUBENT 17 +ENDENTRY 13 diff --git a/exforall/405/40581.x4 b/exforall/405/40581.x4 index 7365acdec..bdce74549 100644 --- a/exforall/405/40581.x4 +++ b/exforall/405/40581.x4 @@ -1,42 +1,59 @@ -ENTRY 40581 20061031 20070521 20060816 4139 -SUBENT 40581001 20061031 20070521 20060816 4139 -BIB 10 22 -TITLE Measurement Of The Absolute Value Of The Alfa - For Uranium-235 In The Neutron Energy Region +ENTRY 40581 20110727 20111003 20110930 4153 +SUBENT 40581001 20110727 20111003 20110930 4153 +BIB 9 25 +TITLE Measurement of the absolute value of the ALFA + for Uranium-235 in the neutron energy region 0.1 - 30. keV. -AUTHOR (G.V.MURADYAN,YU.G.SHCHEPKIN,YU.V.ADAMCHUK, - M.A.VOSKANYAN) +AUTHOR (G.V.Muradyan,Yu.G.Shchepkin,Yu.V.Adamchuk, + M.A.Voskanyan) INSTITUTE (4RUSKUR) -REFERENCE (C,80KIEV,2,119,198009) +REFERENCE (C,80KIEV,2,119,198009) Data table. (C,79KNOX,,438,197910) -MONITOR Absolute Measurements -METHOD (TOF) Multiplicity Spectrometry Of Gamma - And Neutrons. 26m Flight Path. -FACILITY (LINAC) LUE-60 -DETECTOR (NAICR) 46 sectional detector on the base of Na-I(Tl). - Scintillation Volume Is 100 Litres. -ERR-ANALYS (ERR-T) Maximum Total Error + (R,IAE-3769,1983) Data confirmed. +MONITOR Absolute measurements +METHOD (TOF) Multiplicity spectrometry of gamma + and neutrons. 26m flight path. +FACILITY (LINAC,4RUSKUR) LUE-60 +DETECTOR (NAICR) 46 sectional detector on the base of Na-I(Tl) + ROMASHKA-3. Scintillation volume is 100 litres. HISTORY (19810514C) (19851003U) - (19870623U) Reaction Code In SAN 002 Corrected By - Adding 'AV' In SF8 + (19870623U) Reaction code in SAN 002 corrected by + adding 'AV' in SF8 (20061031A) Misprint in Data of Sub.002 was corrected. Dates were corrected for 4-digits year. Second Reference was added. M.M. -ENDBIB 22 + (20110727A) Ref. R,IAE-3769,1983 was added. + Subent 003 was added. + BIB and COMMON information was added . +ENDBIB 25 +NOCOMMON 0 0 +ENDSUBENT 28 +SUBENT 40581002 20110727 20111003 20110930 4153 +BIB 4 17 +REACTION (92-U-235(N,ABS),,ALF,,AV) Averaged over energy +SAMPLE 2 G of metallic uranium. +ERR-ANALYS (ERR-T,,5.5) Maximum total error + (ERR-1) Uncertainty due to uncertainty of efficiencies + ratio EPS-gam/EPS-fis. + (ERR-2,,1.5) Uncertainty due to background, + max. at 10 keV. + (ERR-3,1.5,5.5) Uncertainty due to detector response + function. + (ERR-S,,2.) Statistical uncertainty. + From Table 5 of R,IAE-3769 , %: + ALPHA ERR-3 ERR-1 ERR-2 ERR-T + 1 1.5 2. 1.5 3.5 + 0.5 3. 2. 1.5 4.4 + 0.3 4.5 2. 1.5 5.5 +STATUS (TABLE) Table 3 of C,80KIEV,2,119,1980 + =Table 3 of R,IAE-3769,1983. +ENDBIB 17 COMMON 1 3 -ERR-T +ERR-1 PER-CENT - 5. +2. ENDCOMMON 3 -ENDSUBENT 29 -SUBENT 40581002 20061031 20070521 20060816 4139 -BIB 3 3 -REACTION (92-U-235(N,ABS),,ALF,,AV) Averaged Over Energy -SAMPLE 2 G of metallic Uranium. -STATUS From Table 3 of first Ref. -ENDBIB 3 -NOCOMMON 0 0 DATA 3 22 EN-MIN EN-MAX DATA KEV KEV NO-DIM @@ -63,5 +80,30 @@ KEV KEV NO-DIM 30. 40. 0.368 40. 50. 0.360 ENDDATA 24 -ENDSUBENT 32 -ENDENTRY 2 +ENDSUBENT 50 +SUBENT 40581003 20110727 20111003 20110930 4153 +BIB 4 11 +REACTION (92-U-235(N,ABS),,ALF,,AV) Averaged over energy +ANALYSIS ALPHA-value was measure at thermal region as an + additional control measurement. Analysis of data was th + same as in main cycle. +ERR-ANALYS (ERR-T) Total error + (ERR-1) Uncertainty due to uncertainty of efficiencies + ratio EPS-gam/EPS-fis. + (ERR-2) Uncertainty due to background. + (ERR-3) Uncertainty due to detector response function. + (ERR-S,,1.5) Statistical uncertainty. +STATUS (TABLE) Table 5 of R,IAE-3769,1983. I +ENDBIB 11 +COMMON 4 3 +ERR-1 ERR-2 ERR-3 ERR-T +PER-CENT PER-CENT PER-CENT PER-CENT +2. 0.3 9. 9.3 +ENDCOMMON 3 +DATA 2 1 +EN-DUMMY DATA +KEV NO-DIM +0.0253 0.168 +ENDDATA 3 +ENDSUBENT 23 +ENDENTRY 3 diff --git a/exforall/407/40705.x4 b/exforall/407/40705.x4 index 27d86e8c5..7203d9545 100644 --- a/exforall/407/40705.x4 +++ b/exforall/407/40705.x4 @@ -1,48 +1,68 @@ -ENTRY 40705 861211 20050926 0000 -SUBENT 40705001 861211 20050926 0000 -BIB 13 27 -TITLE MEASUREMENT AND ANALYSIS OF THE NEUTRON EMISSION - SPECTRUM ARISING AT THE 14 MEV NEUTRON BOMBARDMENT - OF NIOBIUM -AUTHOR (A.A.LYCHAGIN,V.A.VINOGRADOV,O.T.GRUDZEVICH,B.V.DEVKIN, - G.V.KOTEL'NIKOVA,V.I.PLYASKIN,O.A.SAL'NIKOV) -INSTITUTE (4CCPFEI) -MONITOR ABSOLUTE MEASUREMENTS -REFERENCE (R,FEI-1385,83) CROSS-SECTION CURVES ARE GIVEN - (J,YK,5/19,34,77) EXPERIMENTAL DETAILS -METHOD (TOF) FLIGHT BASES ARE 2.4M AND 7.M, RESOLUTION 1.3 - AND .65 NSEC/M -DETECTOR (STANK) LIQUID SCINTILLATOR NE-218 AND PHOTOMULTIPLIER +ENTRY 40705 20110812 20111003 20110930 4153 +SUBENT 40705001 20110812 20111003 20110930 4153 +BIB 13 40 +TITLE Measurement and analysis of the neutron emission + spectrum arising at the 14 MeV neutron bombardment + of niobium +AUTHOR (A.A.Lychagin,V.A.Vinogradov,O.T.Grudzevich,B.V.Devkin, + G.V.Kotel'Nikova,V.I.Plyaskin,O.A.Sal'nikov) +INSTITUTE (4RUSFEI) +REFERENCE (R,FEI-1385,1983) Cross-section curves are given +REL-REF (M,,A.A.Lychagin+,R,FEI-923,26,1979) + Method of detector efficiency measurement. + Spectrometer details are in : + (I,,V.B.Anufrienko+,J,VAT/R,1977,(5/19),34,1977) + V.B.Anufrienko+, Universal spectrometer of fast + neutrons by time of flight, Voprosy Atomnoy Nauki i + Tekhniki,ser. Reactorostroenie,iss.(5/19),page 34,1977. +METHOD (TOF) Flight bases are 2.4m and 7.m, resolution 1.3 + and .65 nsec/m . +DETECTOR (STANK) Liquid scintillator NE-218 and photomultiplier XP-2041 - (SCIN) STILBENE,FOR NEUTRON FLUX MONITORING - (LONGC) FOR NEUTRON FLUX MONITORING + Neutron registration threshold 100 keV and 0.5 Mev for + 2.4 m and 7 m, respectively. + Detector efficiency was defined by Cf-252 spectrum + measurement as described in REL-REF of A.A.Lychagin+. + (SCIN) Stilbene crystal of 30 mm diameter, 20mm + thickness, with FEU-30 -for neutron flux monitoring . + (LONGC) For neutron flux monitoring INC-SOURCE (D-T) -SAMPLE CYLINRICAL SAMPLES HIGHT 45 MM AND DIAMETERS 45 - AND 35 MM -ANALYSIS NEUTRON SPECTRUM ANALYSIS ON THE BASIS OF THE STATIS- - TICAL THEORY OF NUCLEAR REACTIONS AND HAUSER-FESHBACH - FORMALISM -STATUS FROM PUBLISHED SOURCES GIVEN UNDER 'REFERENCE' -HISTORY (840411C) COMPILED AT THE CJD - (861211A) SECONDARY NEUTRON SPECTRUM DATA ARE TRANS- - FERRED INTO ENTRY 40851 -CORRECTION CORRECTIONS WERE MADE ON MULTIPLE SCATTERING AND - NEUTRON FLUX ATTENUATION -ENDBIB 27 +FACILITY (ACCEL,4RUSFEI) +SAMPLE Cylindrical samples height 45 mm and diameters 45 + and 35 mm +ANALYSIS Neutron spectrum analysis on the basis of the statis- + tical theory of nuclear reactions and Hauser-Feshbach + formalism. +HISTORY (19840411C) Compiled at the CJD + (19861211A) Secondary neutron spectrum data are trans- + ferred into ENTRY 40851 + (20110812A) M.M. COREL was added. + Reference J,YK,1977,(5/19),34,1977 was deleted as wrong + coded - right ref. is given in REL-REF as free text. +CORRECTION Corrections were made on multiple scattering and + neutron flux attenuation by Monte Carlo method. +ENDBIB 40 NOCOMMON 0 0 -ENDSUBENT 30 -SUBENT 40705002 861211 20050926 0000 -BIB 3 3 +ENDSUBENT 43 +SUBENT 40705002 20110812 20111003 20110930 4153 +BIB 3 10 REACTION (41-NB-93(N,2N)41-NB-92,,SIG) -ANALYSIS CS EXTRACTED FROM THE SECOND-NEUTRONS SPECTRUM -STATUS (PRELM) PRELIMINARY DATUM -ENDBIB 3 +ANALYSIS (INTED) CS extracted from the second-neutrons spectrum, + which was obtained by subtraction of calculated on the + base of theoretical models (parameters for analysis + were found by using exp. data) spectrum of first + neutrons from the measured neutron emission spectrum. + of other authors. +STATUS (TABLE) Text, pages 11, 13 of R,FEI-1385,1983. + (PRELM) Preliminary datum + (COREL,40851003) Different analysis. +ENDBIB 10 NOCOMMON 0 0 DATA 3 1 EN DATA DATA-ERR MEV MB MB 14.3 1370. 110. ENDDATA 3 -ENDSUBENT 11 +ENDSUBENT 18 NOSUBENT 40705003 861211 20050926 0000 ENDENTRY 3 diff --git a/exforall/408/40834.x4 b/exforall/408/40834.x4 index 55f8a5899..f8e64a9fe 100644 --- a/exforall/408/40834.x4 +++ b/exforall/408/40834.x4 @@ -1,29 +1,43 @@ -ENTRY 40834 850114 20050926 0000 -SUBENT 40834001 850114 20050926 0000 -BIB 7 9 -INSTITUTE (4CCPKUR) -REFERENCE (J,AE,57,(4),241,8410) - (C,83KIEV,1,295,8310) -AUTHOR (V.I.MOSTOVOJ,G.I.USTROEV) -TITLE FISSION CROSS-SECTION MEASUREMENT FOR U-235 ISOMER - ON THERMAL NEUTRONS -FACILITY (REAC) REACTOR F-1 -DETECTOR (SOLST) SEMICONDUCTOR BREAKDOWD DETECTOR -HISTORY (850114C) -ENDBIB 9 +ENTRY 40834 20110718 20111003 20110930 4153 +SUBENT 40834001 20110718 20111003 20110930 4153 +BIB 7 17 +INSTITUTE (4RUSKUR) +REFERENCE (J,AE,57,(4),241,198410) + (C,83KIEV,1,295,198310) + (J,SJA,57,(4),692,1984) Engl.translation of J,AE . + #doi:10.1007/BF01123638 +AUTHOR (V.I.Mostovoy,G.I.Ustroev) +TITLE Measurement of the fission cross section of the U-235 + isomer by thermal neutrons . +FACILITY (REAC,4RUSKUR) Reactor F-1 +DETECTOR (SOLST) Semiconductor breakdown detector + FF registration efficiency was defined by Cf-252 + calibration. +HISTORY (19850114C) + (20110718A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + BIB information was added. + Ref. J,SJA was added. +ENDBIB 17 NOCOMMON 0 0 -ENDSUBENT 12 -SUBENT 40834002 860121 20050926 0000 -BIB 2 3 +ENDSUBENT 20 +SUBENT 40834002 20110718 20111003 20110930 4153 +BIB 6 9 REACTION ((92-U-235-M(N,F),,SIG,,SPA)/(92-U-235(N,F),,SIG,,SPA)) -INC-SPECT THERMAL REACTOR SPECTRUM, SPECTRUM TEMPERATURE - 360 DEGREE KELVIN -ENDBIB 3 +INC-SPECT Thermal reactor spectrum, spectrum temperature + 360 degree Kelvin + Thermal neutron beam 0.7E+10 /cm**2/sec. +PART-DET (FF) +SAMPLE U-235-M sample was produced via alpha decay of Pu-239. + Pu-239 monitor sample. +DECAY-DATA (92-U-235-M,26.MIN) +STATUS (TABLE) Text, page 242, of J,AE,57,(4),241,1984. +ENDBIB 9 NOCOMMON 0 0 DATA 3 1 EN-DUMMY DATA DATA-ERR EV NO-DIM NO-DIM - 2.5000E-02 2.2000E+00 4.0000E-01 + 2.5000E-02 2.2 0.4 ENDDATA 3 -ENDSUBENT 11 +ENDSUBENT 17 ENDENTRY 2 diff --git a/exforall/408/40851.x4 b/exforall/408/40851.x4 index b1cfa4c3e..3d24240af 100644 --- a/exforall/408/40851.x4 +++ b/exforall/408/40851.x4 @@ -1,57 +1,68 @@ -ENTRY 40851 920703 20050926 0000 -SUBENT 40851001 920703 20050926 0000 -BIB 14 32 -INSTITUTE (4CCPFEI) -REFERENCE (J,AE,57,266,84) CURVES ARE GIVEN - (C,83KIEV,3,258,8310) CURVES ARE GIVEN - (R,YK-5/19,34,77) EXPERIMENTAL DETAILS -METHOD (TOF) FLIGHT BASE 7 M, RESOLUTION 0.65 NSEC/M AT 0.5MEV - FLIGHT BASE 2.4M,RESOLUTION 1.3 NSEC/M AT 0.1MEV -ANALYSIS SECOND NEUTRONS SPECTRUM WAS OBTAINED BY THE - EXTRACTION FROM THE TOTAL SPECTRUM THAT OF FIRST - NEUTRONS CALCULATED BY THE HAUSER-FESHBACH- - MOLDAUER FORMALISM -STATUS DATA FOR NEUTRON SPECTRA ARE OBTAINED FROM AUTHORS -HISTORY (850311C) - (861211A) NEW SUBENTS INTRODUCED WITH DATA FROM - ENTRY 40705 - (920703U) REACTION CODE IN SAN 002 CHANGED FROM - AUTHOR NAME 'PLJASKIN' CHANGED TO 'PLYASKIN' -TITLE MEASUREMENT AND ANALYSIS OF THE NEUTRON EMISSION - SPECTRUM ARISING AT THE 14 MEV NEUTRON BOMBARDMENT - OF NIOBIUM -AUTHOR (A.A.LYCHAGIN,V.A.VINOGRADOV,O.T.GRUDZEVICH,B.V.DEVKIN, - G.V.KOTEL'NIKOVA,V.I.PLYASKIN,O.A.SAL'NIKOV) -DETECTOR (STANK) LIQUID SCINTILLATOR NE-218 AND PHOTOMULTIPLIER +ENTRY 40851 20110715 20111003 20110930 4153 +SUBENT 40851001 20110715 20111003 20110930 4153 +BIB 15 42 +INSTITUTE (4RUSFEI) +REFERENCE (J,AE,57,266,1984) Curves are given + (C,83KIEV,3,258,198310) Curves are given + (J,SJA,57,(4),726,1984) Engl. translation of J,AE . + #doi:10.1007/BF01123646 +REL-REF (M,,A.A.Lychagin+,R,FEI-1406,1983) + (I,,A.A.Lychagin+,R,FEI-923,1979) + (M,,O.A.Sal'nikov+,R,YK-7,134,1971) Exp. details + and data of previous experiment used for comparison + on Fig.1 of J,AE,57,266,1984. +METHOD (TOF) Flight base 7 m, resolution 0.65 nsec/m at 0.5MeV + Flight base 2.4m,resolution 1.3 nsec/m at 0.1MeV +ANALYSIS Second neutrons spectrum was obtained by the + extraction from the total spectrum that of first + neutrons calculated by the Hauser-Feshbach- + Moldauer formalism . +TITLE Spectrum of secondary neutrons and cross section of + the (n, 2n) reaction at niobium +AUTHOR (A.A.Lychagin,V.A.Vinogradov,O.T.Grudzevich,B.V.Devkin, + G.V.Kotel'nikova,V.I.Plyaskin,O.A.Sal'nikov) +DETECTOR (STANK) Liquid scintillator NE-218 and photomultiplier XP-2041 - (SCIN) STILBENE,FOR NEUTRON FLUX MONITORING - (LONGC) FOR NEUTRON FLUX MONITORING + (SCIN) Stilbene,for neutron flux monitoring + (LONGC) For neutron flux monitoring INC-SOURCE (D-T) -SAMPLE CYLINRICAL SAMPLES HIGHT 45 MM AND DIAMETERS 45 - AND 35 MM -MONITOR NO INFORMATION -ERR-ANALYS ERROR NOT SPECIFIED -CORRECTION CORRECTIONS WERE MADE ON MULTIPLE SCATTERING AND - NEUTRON FLUX ATTENUATION -ENDBIB 32 +SAMPLE Cylindrical samples height 45 mm and diameters 45 + and 35 mm +MONITOR No information +ERR-ANALYS (DATA-ERR) Error not specified +CORRECTION Corrections were made on multiple scattering and + neutron flux attenuation +STATUS (TABLE) Data for neutron spectra are obtained from + authors +HISTORY (19850311C) + (19861211A) New SUBENTs introduced with data from + ENTRY 40705 + (19920703U) REACTION code in SAN 002 changed . + Author namE 'Pljaskin' changed to 'Plyaskin' + (20110715A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + BIB information was added. + Ref. J,SJA was added. +ENDBIB 42 COMMON 1 3 EN MEV 14.3 ENDCOMMON 3 -ENDSUBENT 39 -SUBENT 40851002 920703 20050926 0000 -BIB 5 8 -REACTION (41-NB-93(N,2N)41-NB-92,2,DE) SPECTRUM OF THE - SECOND NEUTRONS +ENDSUBENT 49 +SUBENT 40851002 20110715 20111003 20110930 4153 +BIB 5 9 +REACTION (41-NB-93(N,2N)41-NB-92,2,DE) Spectrum of the + second neutrons EN-SEC (E,N) -HISTORY (920703U) '2' CODE ADDED IN SF4 -ANALYSIS SPECTRUM OBTAINED BY MEANS OF THE EXTRACTION FROM TOT- - AL SPECTRUM THAT OF THE FIRST NEUTRONS OBTAINED BY THE - HAUSER-FESHBACH CALCULATION -STATUS (APRVD) KOTEL'NIKOVA, 850303 -ENDBIB 8 -NOCOMMON +HISTORY (19850303R) Data received. + (19920703U) '2' code added in SF4 +ANALYSIS Spectrum obtained by means of the extraction from tot- + al spectrum that of the first neutrons obtained by the + Hauser-Feshbach calculation +STATUS (APRVD) Kotel'nikova, 1985-03-03 +ENDBIB 9 +NOCOMMON 0 0 DATA 3 21 E DATA ERR-T MEV MB/MEV MB/MEV @@ -77,31 +88,34 @@ MEV MB/MEV MB/MEV 4.0 0.55 0.40 4.2 0.37 0.37 ENDDATA 23 -ENDSUBENT 36 -SUBENT 40851003 861211 20050926 0000 -BIB 2 9 +ENDSUBENT 37 +SUBENT 40851003 20110715 20111003 20110930 4153 +BIB 3 12 REACTION 1(41-NB-93(N,2N)41-NB-92,,SIG) 2(41-NB-93(N,2N)41-NB-92,,SIG) -ANALYSIS 1 TOTAL CROSS-SECTION WAS OBTAINED WITH THE HELP OF - CALCULATIONS, EQUILIBRIUM PART WAS CALCULATED BY THE - HAUSER-FESHBACH-MOLDAUER METHOD PLUS DIRECT PROCESSES - 2 CROSS-SECTION WAS OBTAINED WITH THE HELP OF CALCULA- - TIONS, EQUILIBRIUM PART CALCULATED BY THE HAUSER-FESH- - BACH-MOLDAUER METHOD, NONEQUILIBRIUM PART BY THE EXI- - TON METHOD -ENDBIB 9 +ANALYSIS 1 Total cross-section was obtained with the help of + calculations, equilibrium part was calculated by the + Hauser-Feshbach-Moldauer method plus direct processes + 2 Cross-section was obtained with the help of calcula- + tions, equilibrium part calculated by the Hauser-Fesh- + bach-Moldauer method, nonequilibrium part by the exi- + ton method +STATUS (TABLE) Text, page 267 of J,AE,57,266,1984. + (COREL,40705002) Different analysis. + (DEP,40851002) Measured spectrum was used in analysis. +ENDBIB 12 NOCOMMON 0 0 DATA 4 1 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 MB MB MB MB 1360. 96. 1375. 96. ENDDATA 3 -ENDSUBENT 17 -SUBENT 40851004 890505 20050926 0000 +ENDSUBENT 20 +SUBENT 40851004 20110715 20111003 20110930 4153 BIB 3 3 REACTION (41-NB-93(N,X)0-NN-1,,DE) -STATUS (APRVD) KOTEL'NIKOVA, 840410 -HISTORY (861211T) TRANSFERRED FROM ENTRY 40705 +STATUS (APRVD) Kotel'nikova, 1984-04-10 +HISTORY (19861211T) Transferred from ENTRY 40705 ENDBIB 3 NOCOMMON 0 0 DATA 3 65 diff --git a/exforall/408/40860.x4 b/exforall/408/40860.x4 index 51e34691a..b8eefc4d2 100644 --- a/exforall/408/40860.x4 +++ b/exforall/408/40860.x4 @@ -1,34 +1,45 @@ -ENTRY 40860 850511 20050926 0000 -SUBENT 40860001 850511 20050926 0000 -BIB 11 21 -INSTITUTE (4CCPIJI) -REFERENCE (J,AE,57,(4),260,84) - (C,83KIEV,3,43,8310) -AUTHOR (V.P.VERTEBNYJ,P.N.VORONA,A.I.KAL'CHENKO,V.G.KRIVENKO, - V.JU.CHERVJAKOV) -TITLE TOTAL NEUTRON CROSS-SECTIONS FOR RADIOACTIV ISOTOPE - GD-153 (HALF-LIFE = 241.6 DAYS) AND STABLE ISOTOPE - GD-152 -FACILITY (REAC) -SAMPLE BEFORE IRRADIATION SAMPLE CONTAINED GD-152 -30 PC, - GD-154 - 9.5 PC, GD-155 - 22.1 PC, GD-156 - 14.9 PC, - GD-157 - 8.5 PC, GD-158 - 9.1 PC - GADOLINIUM OXIDE, WEIGHT 71.64 MILLIGRAM, THICKNESS - 6.83E20 1/CM2 -METHOD (TOF) RESOLUTION 0.055 - 0.92 MICROSEC/M - FLIGHT BASE 69.47 M -DETECTOR (PROPC) BATTERY OF HE-3 COUNTERS -STATUS (APRVD) VERTEBNYJ, 8505 -HISTORY (850511C) -ERR-ANALYS (ERR-1) ERROR DUE TO THE NUCLEI CONCENTRATION - UNCERTAINTY -ENDBIB 21 +ENTRY 40860 20110713 20111003 20110930 4153 +SUBENT 40860001 20110713 20111003 20110930 4153 +BIB 11 30 +INSTITUTE (4UKRIJD) +REFERENCE (J,AE,57,(4),260,1984) Figures only. + (J,SJA,57,(4),718,1984) Engl. transl. of J,AE. + #doi:10.1007/BF01123644 + (C,83KIEV,3,43,198310) Figures only. +AUTHOR (V.P.Vertebnyy,P.N.Vorona,A.I.Kal'chenko,V.G.Krivenko, + V.Yu.Chervjakov) +TITLE Total neutron cross-sections for radioactive isotope + Gd-153 (half-life = 241.6 days) and stable isotope + Gd-152 . +FACILITY (REAC,4UKRIJD) WWR-M reactor. +SAMPLE Before irradiation sample contained Gd-152 -30 % , + Gd-154 - 9.5 % , Gd-155 - 22.1 % , Gd-156 - 14.9 % , + Gd-157 - 8.5 % , Gd-158 - 9.1 % + Gadolinium oxide, weight 71.64 milligram, thickness + 6.83e20 1/cm2. + Gd-153 sample was obtained by triple irradiation of + Gd-152 in reactor. +METHOD (TOF) Resolution 0.055 - 0.92 microsec/m + flight base 69.47 m + (TRN) transmission were measured. +DETECTOR (PROPC) Battery of He-3 counters +STATUS (APRVD) Vertebnyy, 1985-05 +HISTORY (19850511C) + (20110713A) Upper -> lower case correction. + Dates were corrected for 4-digits year. + BIB information was added. + Ref. J,SJA was added. +ERR-ANALYS (ERR-1) Error due to the nuclei concentration + uncertainty +ENDBIB 30 NOCOMMON 0 0 -ENDSUBENT 24 -SUBENT 40860002 850511 20050926 0000 -BIB 1 1 +ENDSUBENT 33 +SUBENT 40860002 20110713 20111003 20110930 4153 +BIB 2 3 REACTION (64-GD-152(N,TOT),,SIG) -ENDBIB 1 +STATUS (TABLE) Data were received from V.Vertebnyj. + Data are given on Fig.1v of J,AE,57,(4),260,1984 +ENDBIB 3 COMMON 1 3 ERR-1 PER-CENT @@ -78,12 +89,14 @@ EV B B B 2.6200E-02 9.5000E+02 2.5300E-02 1.0250E+03 6.0000E+01 2.3000E+02 ENDDATA 42 -ENDSUBENT 52 -SUBENT 40860003 850511 20050926 0000 -BIB 2 2 +ENDSUBENT 54 +SUBENT 40860003 20110713 20111003 20110930 4153 +BIB 3 4 REACTION (64-GD-153(N,TOT),,SIG) DECAY-DATA (64-GD-153,241.6D) -ENDBIB 2 +STATUS (TABLE) Data were received from V.Vertebnyj. + Data are given on Fig.1v of J,AE,57,(4),260,1984 +ENDBIB 4 COMMON 1 3 ERR-1 PER-CENT @@ -133,5 +146,5 @@ EV B B B 2.6200E-02 1.4909E+04 2.5300E-02 1.4470E+04 7.7000E+02 3.0000E+03 ENDDATA 42 -ENDSUBENT 53 +ENDSUBENT 55 ENDENTRY 3 diff --git a/exforall/408/40862.x4 b/exforall/408/40862.x4 index 43d1103d7..43f41d26e 100644 --- a/exforall/408/40862.x4 +++ b/exforall/408/40862.x4 @@ -1,29 +1,54 @@ -ENTRY 40862 860417 20050926 0000 -SUBENT 40862001 860417 20050926 0000 -BIB 9 13 -INSTITUTE (4CCPCCP) -REFERENCE (J,AE,57,(3),179,8409) -AUTHOR (A.A.SARKISOV,I.N.MARTEM'JANOV,A.M.BOGUSLAVSKIJ, - V.N.IVANOV,G.N.IVANOV) -TITLE RESONANCE EFFECTS INVESTIGATION FOR FAST NEUTRON - INTERACTION WITH NUCLEI FE-6 IN THE ENERGY RANGE - 0.2 - 0.8 MEV -FACILITY (REAC) RESEARCH REACTOR IR-100 -METHOD RESONANCE FILTER METHOD -DETECTOR (SCIN) STILBENE DETECTOR 30*30 CM -COMMENT THICKNESS IN DATA SECTION REFERS TO THE FILTER - THICKNESS -HISTORY (850521C) -ENDBIB 13 +ENTRY 40862 20110715 20111003 20110930 4153 +SUBENT 40862001 20110715 20111003 20110930 4153 +BIB 12 36 +INSTITUTE (4RUSMIF) +REFERENCE (J,AE,57,(3),179,198409) + (J,SJA,57,(3),620,1984) Engl.translation of J,AE,57 . + #doi:10.1007/BF01122332 +REL-REF (I,,L.V.Konstantinov+,J,AE,29,(6),453,1970) + IR-10 research and training reactor details. + (I,,L.V.Konstantinov+,J,SJA,29,(6),1227,1970) + Engl.translation of J,AE,29 + (I,,Yu.M.Bulkin+,J,AE,21,(5),363,1966) + IR-10 research and training reactor details. + (I,,Yu.M.Bulkin+,J,SJA,21,(5),1012,1966) + Engl.translation of J,AE,21. +AUTHOR (A.A.Sarkisov,I.N.Martem'yanov,A.M.Boguslavskij, + V.N.Ivanov,G.N.Ivanov) +TITLE Resonance effects in the interaction of 0.2-0.8-MeV + neutrons with Fe-56 nuclei. +FACILITY (REAC) Research reactor IR-100 +INC-SOURCE (REAC) Collimator - 4.1m long, diameter 46 mm. +METHOD (FNB) Resonance filter method + (PSD) Neutron-gamma pulse shape discrimination, + energy threshold about 100 keV. +DETECTOR (SCIN) Stilbene detector 30*30 cm +SAMPLE Cylindrical filters of 0.05 m diameter, Fe-56 - 98%. + Scatterers- hollow cylinders of 0.05 m hight,different + thickness of wall. + Scatterer - in beam and out beam to estimate + backgrouns. +COMMENT Thickness in DATA section refers to the filter + thickness. +HISTORY (19850521C) + (20110715A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + BIB information was added. + Ref. J,SJA was added. + THICKNESS -> MISC according to the comment of + N.Otsuka (NDS,IAEA) . +ENDBIB 36 NOCOMMON 0 0 -ENDSUBENT 16 -SUBENT 40862002 860417 20050926 0000 -BIB 1 1 -REACTION (26-FE-56(N,TOT),,SIG,,AV) AVERAGED OVER ENERGY -ENDBIB 1 +ENDSUBENT 39 +SUBENT 40862002 20110715 20111003 20110930 4153 +BIB 3 3 +REACTION (26-FE-56(N,TOT),,SIG,,AV) Averaged over energy +MISC-COL (MISC) Thickness of filter. +STATUS (TABLE) Table 1 of J,AE,57,(3),179,1984. +ENDBIB 3 NOCOMMON 0 0 DATA 5 7 -EN-MIN EN-MAX THICKNESS DATA DATA-ERR +EN-MIN EN-MAX MISC DATA DATA-ERR MEV MEV M B B 4.0000E-01 8.0000E-01 0.0000E+00 3.3000E+00 7.0000E-01 4.0000E-01 8.0000E-01 2.0000E-02 3.1000E+00 1.0000E-01 @@ -33,14 +58,16 @@ MEV MEV M B B 4.0000E-01 8.0000E-01 1.8000E-01 2.5000E+00 2.0000E-01 4.0000E-01 8.0000E-01 2.2000E-01 2.4000E+00 3.0000E-01 ENDDATA 9 -ENDSUBENT 15 -SUBENT 40862003 860417 20050926 0000 -BIB 1 1 -REACTION (26-FE-56(N,TOT),,SIG,,AV) AVERAGED OVER ENERGY -ENDBIB 1 +ENDSUBENT 17 +SUBENT 40862003 20110715 20111003 20110930 4153 +BIB 3 3 +REACTION (26-FE-56(N,TOT),,SIG,,AV) Averaged over energy +MISC-COL (MISC) Thickness of filter. +STATUS (TABLE) Table 1 of J,AE,57,(3),179,1984. +ENDBIB 3 NOCOMMON 0 0 DATA 5 7 -EN-MIN EN-MAX THICKNESS DATA DATA-ERR +EN-MIN EN-MAX MISC DATA DATA-ERR MEV MEV M B B 2.0000E-01 4.0000E-01 0.0000E+00 3.0300E+00 9.0000E-02 2.0000E-01 4.0000E-01 2.0000E-02 2.9000E+00 2.0000E-01 @@ -50,14 +77,17 @@ MEV MEV M B B 2.0000E-01 4.0000E-01 1.8000E-01 2.3000E+00 2.0000E-01 2.0000E-01 4.0000E-01 2.2000E-01 2.2000E+00 3.0000E-01 ENDDATA 9 -ENDSUBENT 15 -SUBENT 40862004 860417 20050926 0000 -BIB 1 1 -REACTION (26-FE-56(N,SCT)26-FE-56,,SIG,,AV) AVERAGED OVER -ENDBIB 1 +ENDSUBENT 17 +SUBENT 40862004 20110715 20111003 20110930 4153 +BIB 3 4 +REACTION (26-FE-56(N,SCT)26-FE-56,,SIG,,AV) Averaged over + energy group. +MISC-COL (MISC) Thickness of filter. +STATUS (TABLE) Table 1 of J,AE,57,(3),179,1984. +ENDBIB 4 NOCOMMON 0 0 DATA 5 7 -EN-MIN EN-MAX THICKNESS DATA DATA-ERR +EN-MIN EN-MAX MISC DATA DATA-ERR MEV MEV M B B 4.0000E-01 8.0000E-01 0.0000E+00 3.3000E+00 6.0000E-02 4.0000E-01 8.0000E-01 2.0000E-02 3.1000E+00 8.0000E-02 @@ -67,14 +97,17 @@ MEV MEV M B B 4.0000E-01 8.0000E-01 1.8000E-01 2.5000E+00 2.0000E-01 4.0000E-01 8.0000E-01 2.2000E-01 2.4000E+00 2.0000E-01 ENDDATA 9 -ENDSUBENT 15 -SUBENT 40862005 860417 20050926 0000 -BIB 1 1 -REACTION (26-FE-56(N,SCT)26-FE-56,,SIG,,AV) AVERAGED OVER ENERGY -ENDBIB 1 +ENDSUBENT 18 +SUBENT 40862005 20110715 20111003 20110930 4153 +BIB 3 4 +REACTION (26-FE-56(N,SCT)26-FE-56,,SIG,,AV) Averaged over energy + group. +MISC-COL (MISC) Thickness of filter. +STATUS (TABLE) Table 1 of J,AE,57,(3),179,1984. +ENDBIB 4 NOCOMMON 0 0 DATA 5 7 -EN-MIN EN-MAX THICKNESS DATA DATA-ERR +EN-MIN EN-MAX MISC DATA DATA-ERR MEV MEV M B B 2.0000E-01 4.0000E-01 0.0000E+00 3.0000E+00 9.0000E-02 2.0000E-01 4.0000E-01 2.0000E-02 2.9000E+00 1.0000E-01 @@ -84,5 +117,5 @@ MEV MEV M B B 2.0000E-01 4.0000E-01 1.8000E-01 2.3000E+00 3.0000E-01 2.0000E-01 4.0000E-01 2.2000E-01 2.2000E+00 3.0000E-01 ENDDATA 9 -ENDSUBENT 15 +ENDSUBENT 18 ENDENTRY 5 diff --git a/exforall/408/40863.x4 b/exforall/408/40863.x4 index 124dc0f18..3666249df 100644 --- a/exforall/408/40863.x4 +++ b/exforall/408/40863.x4 @@ -1,40 +1,63 @@ -ENTRY 40863 860417 20050926 0000 -SUBENT 40863001 860417 20050926 0000 -BIB 11 17 -INSTITUTE (4CCPRI) -REFERENCE (J,AE,57,(3),210,8409) -AUTHOR (JU.N.TROFIMOV) -TITLE CADMIUM-111(N,INL)CADMIUM-111M REACTION CROSS-SECTION - IN THE ENERGY RANGE FROM THE THRESHOLD TO 2.2 MEV +ENTRY 40863 20110715 20111003 20110930 4153 +SUBENT 40863001 20110715 20111003 20110930 4153 +BIB 12 32 +INSTITUTE (4RUSRI) +REFERENCE (J,AE,57,(3),210,198409) + (J,SJA,57,(3),670,1984) Engl. translation of J,AE . + #doi:10.1007/BF01122346 +AUTHOR (YU.N.Trofimov) +TITLE Cross section of the C-111(n,n')Cd-111m reaction in + the interval extending from the threshold energy to + 2.2 MeV. FACILITY (VDG) -SAMPLE CD-110 CONTENT IS 0.35 PC, CD-111 CONTENT IS 95.1 PC, - CD-112 CONTENT IS 2.98 PC, CD-113 CONTENT IS 0.48 PC, - CD-114 CONTENT IS 0.93 PC, CD-116 CONTENT IS 0.16 PC +INC-SOURCE (P-T) T-Ti targets . +SAMPLE Cd-110 content is 0.35 %, Cd-111 content is 95.1 %, + Cd-112 content is 2.98 %, Cd-113 content is 0.48 %, + Cd-114 content is 0.93 %, Cd-116 content is 0.16 %. + Sample mass 20 mg, diameter 6 mm. METHOD (ACTIV) -DETECTOR (GELI) -HISTORY (850521C) -CORRECTION ON SCATTERED NEUTRONS - 3+-1 PC, ON PULSE ADDITION - - 1.5+-0.3 PC, -ERR-ANALYS (ERR-1) ERROR DUE TO THE GE-LI DETECTOR EFFICIENCY - (ERR-2) CD-111-M ACTIVITY ERROR - (ERR-3) IN-116-M ACTIVITY ERROR -ENDBIB 17 +DETECTOR (SOLST) Two detectors of diameter 6mm , thickness 0.2mm + to measure neutron flux. + (SPEC,GELI) Ge(Li) spectrometer with detector of + 38 cm**3 volume, resolution 3 keV for 1332 keV line, + to measure energy and intensity of gamma-peaks. + Spectrometer was calibrated by standard sources. +HISTORY (19850521C) + (20110715A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + BIB information was added. + Ref. J,SJA was added. +CORRECTION On scattered neutrons - 3+-1 % , on pulse addition - + 1.5+-0.3 % , +ERR-ANALYS (ERR-1) Error due to the Ge-Li Detector Efficiency + (ERR-2) Cd-111-m activity error + (ERR-3) In-116-m activity error + (ERR-T) Total error. +ENDBIB 32 COMMON 3 3 ERR-1 ERR-2 ERR-3 PER-CENT PER-CENT PER-CENT 4.0000E+00 5.0000E-01 1.0000E+00 ENDCOMMON 3 -ENDSUBENT 24 -SUBENT 40863002 860417 20050926 0000 -BIB 4 6 +ENDSUBENT 39 +SUBENT 40863002 20110715 20111003 20110930 4153 +BIB 7 10 REACTION (48-CD-111(N,INL)48-CD-111-M,,SIG) DECAY-DATA (48-CD-111-M,49.1MIN,DG,245.35,0.942) MONITOR (49-IN-115(N,G)49-IN-116-M,,SIG) (49-IN-115(N,INL)49-IN-115-M,,SIG) DECAY-MON (49-IN-115-M,,DG,336.25) - (49-IN-116-M,54.15MIN,DG,416.98,0.38) -ENDBIB 6 -NOCOMMON 0 0 + (49-IN-116-M,54.15MIN,DG,416.98,0.33) + 54.15+-0.05 min, 0.33+-0.01 - data from REL-REF. +MONIT-REF (,,R,BNL-NCS-50446,1975) ENDF/B-V Dosimetry File. +REL-REF (R,,N.G.Gusev+,B,GUSEV,,1977) Ref. for DECAY-MON data. +STATUS (TABLE) Table of J,AE,57,(3),210,1984 +ENDBIB 10 +COMMON 2 3 +ERR-HL ERR-IDD +MIN NO-DIM +0.1 0.001 +ENDCOMMON 3 DATA 6 14 EN EN-RSL-FW DATA ERR-T MONIT1 MONIT2 MEV MEV MB MB MB MB @@ -53,5 +76,5 @@ MEV MEV MB MB MB MB 2.1000E+00 8.0000E-02 2.3200E+02 1.8000E+01 1.1500E+02 2.7000E+02 2.2000E+00 8.0000E-02 2.5300E+02 2.0000E+01 1.0800E+02 2.8000E+02 ENDDATA 16 -ENDSUBENT 27 +ENDSUBENT 35 ENDENTRY 2 diff --git a/exforall/408/40873.x4 b/exforall/408/40873.x4 index c79b2f06c..f45b51d3b 100644 --- a/exforall/408/40873.x4 +++ b/exforall/408/40873.x4 @@ -1,38 +1,52 @@ -ENTRY 40873 860417 20050926 0000 -SUBENT 40873001 860417 20050926 0000 -BIB 10 19 -INSTITUTE (4CCPNIR) -REFERENCE (C,83KIEV,2,294,8309) NEW ANALYSIS OF THE OLD DATA - (R,NIIAR-P1-22/356,78) OLD EXPERIMENTAL DATA -AUTHOR (A.A.BOJCOV,A.F.SEMENOV,B.I.STAROSTOV) -TITLE RELATIVE MEASUREMENTS OF THE SRECTRA OF PROMPT FISSION - NEUTRONS FOR THERMAL NEUTRON FISSION OF THE NUCLEI - U-233, U-235, PU-239 IN THE ENERGY RANGE 0.01 - 5 MEV -INC-SPECT THERMAL NEUTRONS -METHOD (TOF) -MONITOR (98-CF-252(0,F),PR,DE,N) - REFERENCE(STANDARD) SPECTRUM OF CF-252 SPONTANEOUS - FISSION NEUTRONS IS MAXWELLIAN WITH TEMPERATURE - 1.418 +- 0.024 MEV -STATUS (RNORM) RENORMALIZED BY THE AUTHORS, ORIGINAL DATA ARE - IN (R,NIIAR-P-22/356,78) +ENTRY 40873 20110125 20111003 20110930 4153 +SUBENT 40873001 20110125 20111003 20110930 4153 +BIB 12 24 +INSTITUTE (4RUSNIR) +REFERENCE (C,83KIEV,2,294,198309) New analysis of the old data + (R,NIIAR-P1-22/356,1978) Old experimental data +AUTHOR (A.A.Boytsov,A.F.Semenov,B.I.Starostov) +TITLE Relative measurements of the spectra of prompt fission + neutrons for thermal neutron fission of the nuclei + U-233, U-235, pu-239 in the energy range 0.01 - 5 MeV +FACILITY (REAC) SM-2 reactor. +INC-SPECT Thermal neutrons +METHOD (TOF) Time resolution 5 ns. +MONITOR (98-CF-252(0,F),PR,NU/DE) + Reference(standard) spectrum of Cf-252 spontaneous + fission neutrons is Maxwellian with temperature + 1.418 +- 0.024 MeV +MONIT-REF (40930002,B.I.Starostov+,J,YK,1985,(3),16,1985) +STATUS Renormalized by the authors, original data are + in (R,NIIAR-P-22/356,1978) (APRVD) -HISTORY (851015C) COMPILED AT THE CENTRE -ERR-ANALYS (ERR-T) TOTAL ERROR CONTAINES STATISTICAL ONE, FLIGHT - TIME AND BASE ERRORS, DETECTOR EFFIC. ERROR -ENDBIB 19 + (TABLE) From author. +HISTORY (19851015C) Compiled at the centre + (20110125A) Entry was corrected -see HISTORY in Subents + A.A.Bojcov -> A.A.Boytsov. +ERR-ANALYS (ERR-T) Total error contains statistical one, flight + time and base errors, detector effic. error +ENDBIB 24 COMMON 1 3 EN-DUMMY EV 2.5300E-02 ENDCOMMON 3 -ENDSUBENT 26 -SUBENT 40873002 851015 20050926 0000 -BIB 1 2 -REACTION (92-U-233(N,F),PR,DE,N,REL) RELATIVE TO THE MAXWELL - SPECTRUM -ENDBIB 2 -NOCOMMON 0 0 +ENDSUBENT 31 +SUBENT 40873002 20110125 20111003 20110930 4153 +BIB 3 7 +REACTION (92-U-233(N,F),PR,NU/DE,,MXD) Relative to the Maxwell + spectrum +COMMENT Of compiler. KT-NRM was added as given in + C,83KIEV,2,294,1983: 1.336+-0.035 -derived from fitting + of spectrum, 1.34 MeV - used in ratio to Maxwellian. +HISTORY (20110125A) REL -> MXD, DE -> NU/DE. KT-NRM was added. + COMMENT was added. +ENDBIB 7 +COMMON 1 3 +KT-NRM +MEV + 1.34 +ENDCOMMON 3 DATA 3 37 E DATA ERR-T MEV NO-DIM PER-CENT @@ -74,25 +88,37 @@ MEV NO-DIM PER-CENT 3.9000E+00 1.0000E+00 8.3000E+00 4.5000E+00 1.0200E+00 8.5000E+00 ENDDATA 39 -ENDSUBENT 46 -SUBENT 40873003 851015 20050926 0000 -BIB 2 2 -REACTION (92-U-233(N,F),PR,AKE,N) +ENDSUBENT 55 +SUBENT 40873003 20110125 20111003 20110930 4153 +BIB 3 5 +REACTION (92-U-233(N,F)0-NN-1,PR,KE) STATUS (DEP,40873002) -ENDBIB 2 +HISTORY (20110125A) AKE -> KE according to NDS, IAEA opinion. + N was deleted fron SF7, 0-NN-1 was added in SF4 + according to the comment of N.Otsuka (NDS, IAEA). +ENDBIB 5 NOCOMMON 0 0 DATA 2 1 DATA ERR-T MEV MEV 2.0040E+00 5.2500E-02 ENDDATA 3 -ENDSUBENT 10 -SUBENT 40873004 851015 20050926 0000 -BIB 1 2 -REACTION (92-U-235(N,F),PR,DE,N,REL) RELATIVE TO THE MAXWELL - SPECTRUM -ENDBIB 2 -NOCOMMON 0 0 +ENDSUBENT 13 +SUBENT 40873004 20110125 20111003 20110930 4153 +BIB 3 7 +REACTION (92-U-235(N,F),PR,NU/DE,,MXD) Relative to the Maxwell + spectrum +COMMENT Of compiler. KT-NRM was added as given in + C,83KIEV,2,294,1983: 1.296+-0.035 -derived from fitting + of spectrum, 1.313 MeV - used in ratio to Maxwellian. +HISTORY (20110125A) REL -> MXD, DE -> NU/DE. + KT-NRM was added as given in C,83KIEV,2,294,1983. +ENDBIB 7 +COMMON 1 3 +KT-NRM +MEV + 1.313 +ENDCOMMON 3 DATA 3 37 E DATA ERR-T MEV NO-DIM PER-CENT @@ -134,25 +160,37 @@ MEV NO-DIM PER-CENT 3.9000E+00 1.0300E+00 8.3000E+00 4.5000E+00 1.0300E+00 8.5000E+00 ENDDATA 39 -ENDSUBENT 46 -SUBENT 40873005 851015 20050926 0000 -BIB 2 2 -REACTION (92-U-235(N,F),PR,AKE,N) +ENDSUBENT 55 +SUBENT 40873005 20110125 20111003 20110930 4153 +BIB 3 5 +REACTION (92-U-235(N,F)0-NN-1,PR,KE) STATUS (DEP,40873004) -ENDBIB 2 +HISTORY (20110125A) AKE -> KE according to NDS, IAEA opinion. + N was deleted fron SF7, 0-NN-1 was added in SF4 + according to the comment of N.Otsuka (NDS, IAEA). +ENDBIB 5 NOCOMMON 0 0 DATA 2 1 DATA ERR-T MEV MEV 1.9440E+00 5.2000E-02 ENDDATA 3 -ENDSUBENT 10 -SUBENT 40873006 851015 20050926 0000 -BIB 1 2 -REACTION (94-PU-239(N,F),PR,DE,N,REL) RELATIVE TO THE MAXWELL - SPECTRUM -ENDBIB 2 -NOCOMMON 0 0 +ENDSUBENT 13 +SUBENT 40873006 20110125 20111003 20110930 4153 +BIB 3 7 +REACTION (94-PU-239(N,F),PR,NU/DE,,MXD) Relative to the Maxwell + spectrum +COMMENT Of compiler. KT-NRM was added as given in + C,83KIEV,2,294,1983: 1.382+-0.035 -derived from fitting + of spectrum, 1.382 MeV - used in ratio to Maxwellian. +HISTORY (20110125A) REL -> MXD, DE -> NU/DE. + KT-NRM was added as given in C,83KIEV,2,294,1983. +ENDBIB 7 +COMMON 1 3 +KT-NRM +MEV + 1.382 +ENDCOMMON 3 DATA 3 37 E DATA ERR-T MEV NO-DIM PER-CENT @@ -194,17 +232,20 @@ MEV NO-DIM PER-CENT 3.9000E+00 1.0200E+00 8.3000E+00 4.5000E+00 1.0300E+00 8.5000E+00 ENDDATA 39 -ENDSUBENT 46 -SUBENT 40873007 851015 20050926 0000 -BIB 2 2 -REACTION (94-PU-239(N,F),PR,AKE,N) +ENDSUBENT 55 +SUBENT 40873007 20110125 20111003 20110930 4153 +BIB 3 5 +REACTION (94-PU-239(N,F)0-NN-1,PR,KE) STATUS (DEP,40873006) -ENDBIB 2 +HISTORY (20110125A) AKE -> KE according to NDS, IAEA opinion. + N was deleted fron SF7, 0-NN-1 was added in SF4 + according to the comment of N.Otsuka (NDS, IAEA). +ENDBIB 5 NOCOMMON 0 0 DATA 2 1 DATA ERR-T MEV MEV 2.0730E+00 5.2000E-02 ENDDATA 3 -ENDSUBENT 10 +ENDSUBENT 13 ENDENTRY 7 diff --git a/exforall/408/40874.x4 b/exforall/408/40874.x4 index 065be1beb..a6c32eec7 100644 --- a/exforall/408/40874.x4 +++ b/exforall/408/40874.x4 @@ -1,42 +1,51 @@ -ENTRY 40874 860417 20050926 0000 -SUBENT 40874001 860417 20050926 0000 -BIB 11 14 -INSTITUTE (4CCPNIR) -REFERENCE (C,83KIEV,2,298,8310) -AUTHOR (A.A.BOJCOV,B.I.STAROSTOV) -TITLE HIGH PRECISION PROMPT NEUTRON SPECTRUM MEASUREMENT - FROM CF-252 SPONTANEOUS FISSION IN THE ENERGY RANGE - 0.01 - 3 MEV -INC-SOURCE (CF252) -SAMPLE CF-252 LAYER ON A THIN PLATINUM SHEET -METHOD (TOF) FLIGHT BASE .51 M -DETECTOR (SCIN) ANTRACEN SCINTILLATION DETECTOR - (FISCH) U-235 FISSION CHAMBER -MONITOR ABSOLUTE MEASUREMENT +ENTRY 40874 20110125 20111003 20110930 4153 +SUBENT 40874001 20110125 20111003 20110930 4153 +BIB 10 15 +INSTITUTE (4RUSNIR) +REFERENCE (C,83KIEV,2,298,198310) +AUTHOR (A.A.Boytsov,B.I.Starostov) +TITLE High precision prompt neutron spectrum measurement + from Cf-252 spontaneous fission in the energy range + 0.01 - 3 MeV +SAMPLE Cf-252 layer on platinum sheet of 0.01mm thickness . +METHOD (TOF) Flight base .51 m +MONITOR (92-U-235(N,F),,SIG) For U-235 IC efficiency. +MONIT-REF (,V.A.Kon'shin+,R,TMO-22,1978) STATUS (APRVD) -HISTORY (851016C) COMPILED IN CJD -ENDBIB 14 +HISTORY (19851016C) Compiled in CJD + (20110125A) Entry corrected according to comments of + V.Pronyaev (CJD) and NDS IAEA. + A.A.Bojcov -> A.A.Boytsov. +ENDBIB 15 NOCOMMON 0 0 -ENDSUBENT 17 -SUBENT 40874002 851016 20050926 0000 -BIB 3 11 -REACTION (98-CF-252(0,F),PR,DE,N,REL) ABSOLUTE VALUE NORMALIZED +ENDSUBENT 18 +SUBENT 40874002 20110125 20111003 20110930 4153 +BIB 6 19 +REACTION (98-CF-252(0,F),PR,NU/DE) Absolute value normalized +DETECTOR (SCIN) Anthracene scintillation detector for neutron + registration + (IOCH) For Cf-252 FF registration. Weight about 2.5 g. + FF registration efficiency 97+-2 % . EN-SEC (E,N) -ERR-ANALYS (ERR-1) SUM OF STATISTICAL ERROR, ERROR DUE TO THE - RANDOM COINCIDENCE IN THE DETECTORS, ERROR - DUE TO THE RECYCLING NEUTRONS, ERROR DUE TO - THE EXPERIMENTAL HALL BACKGROUND - (ERR-2) ERROR DUE TO THE FLIGHT TIME UNCERTAINTIES - (ERR-3) ERROR CAUSED BY THE NEUTRON SCATTERING ON - THE DETECTOR WALLS AND ON THE AIR ATOMS - (ERR-4) ERROR CAUSED BY THE DETECTOR EFFICIENCY - UNCERTAINTY -ENDBIB 11 +ERR-ANALYS (ERR-1) Sum of statistical error, error due to the + random coincidence in the detectors, error + due to the recycling neutrons, error due to + the experimental hall background + (ERR-2) Error due to the flight time uncertainties + (ERR-3) Error caused by the neutron scattering on + the detector walls and on the air atoms + (ERR-4) Error caused by the detector efficiency + uncertainty + (ERR-T) Total error. +STATUS (TABLE) From author. +HISTORY (20110125A) REL was deleted. + DE -> NU/DE. ARB-UNITS -> PT/FIS/MEV . +ENDBIB 19 NOCOMMON 0 0 DATA 8 55 E E-RSL DATA ERR-1 ERR-2 ERR-3 ERR-4 ERR-T -MEV MEV ARB-UNITS PER-CENT PER-CENT PER-CENT +MEV MEV PT/FIS/MEV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 9.1000E-02 5.0000E-03 7.2600E-01 3.2000E+00 5.0000E-01 7.0000E-02 2.6000E+00 4.2000E+00 @@ -149,15 +158,24 @@ PER-CENT PER-CENT 2.0500E+00 5.2000E-01 8.6900E-01 8.0000E-01 1.7000E+00 7.0000E-02 2.2000E+00 3.0000E+00 ENDDATA 114 -ENDSUBENT 130 -SUBENT 40874003 851016 20050926 0000 -BIB 3 4 -REACTION (98-CF-252(0,F),PR,DE,N,REL) RATIO TO THE MAXWELL WITH - TEMPERATURE 1.42 MEV -DETECTOR (IOCH) THIN-WALL IONIZATION CHAMBER +ENDSUBENT 138 +SUBENT 40874003 20110125 20111003 20110930 4153 +BIB 5 9 +REACTION (98-CF-252(0,F),PR,NU/DE,,MXD) Ratio to the Maxwell + with temperature 1.42 MeV +DETECTOR (IOCH) Thin-wall ionization chamber with eight U-235 + fission layers for neutron registration . EN-SEC (E,N) -ENDBIB 4 -NOCOMMON 0 0 +STATUS (TABLE) From author. + Data are on Fig. of C,83KIEV,2,298,1983 +HISTORY (20110125A) DE,N,REL -> NU/DE,,MXD. + KT-NRM was added. +ENDBIB 9 +COMMON 1 3 +KT-NRM +MEV + 1.42 +ENDCOMMON 3 DATA 3 24 E DATA ERR-T MEV NO-DIM PER-CENT @@ -186,15 +204,24 @@ MEV NO-DIM PER-CENT 8.9000E-01 9.8000E-01 4.3000E+00 1.0500E+00 1.0100E+00 4.3000E+00 ENDDATA 26 -ENDSUBENT 35 -SUBENT 40874004 851016 20050926 0000 -BIB 3 4 -REACTION (98-CF-252(0,F),PR,DE,N,REL) RATIO TO THE MAXWELL WITH - TEMPERATURE 1.42 MEV -DETECTOR (IOCH) 'GSD' +ENDSUBENT 44 +SUBENT 40874004 20110125 20111003 20110930 4153 +BIB 5 9 +REACTION (98-CF-252(0,F),PR,NU/DE,,MXD) Ratio to the Maxwell + with temperature 1.42 MeV +DETECTOR (IOCH) Gas scintillating detector - ionization chamber + with 235U metallic radiator EN-SEC (E,N) -ENDBIB 4 -NOCOMMON 0 0 +STATUS (TABLE) From author. + Data are on Fig. of C,83KIEV,2,298,1983 +HISTORY (20110125A) DE,N,REL -> NU/DE,,MXD. + KT-NRM was added. +ENDBIB 9 +COMMON 1 3 +KT-NRM +MEV + 1.42 +ENDCOMMON 3 DATA 3 24 E DATA ERR-T MEV NO-DIM PER-CENT @@ -223,5 +250,5 @@ MEV NO-DIM PER-CENT 3.2600E+00 1.0170E+00 4.3000E+00 3.6800E+00 1.0210E+00 4.3000E+00 ENDDATA 26 -ENDSUBENT 35 +ENDSUBENT 44 ENDENTRY 4 diff --git a/exforall/408/40890.x4 b/exforall/408/40890.x4 index e43370577..b5ae4e28c 100644 --- a/exforall/408/40890.x4 +++ b/exforall/408/40890.x4 @@ -1,50 +1,56 @@ -ENTRY 40890 20010319 20010718 20050926 0000 -SUBENT 40890001 20010319 20010718 20050926 0000 -BIB 13 24 +ENTRY 40890 20100701 20111003 20110930 4153 +SUBENT 40890001 20100701 20111003 20110930 4153 +BIB 11 27 INSTITUTE (4RUSFEI) -AUTHOR (L.E.KAZAKOV,V.N.KONONOV,E.D.POLETAEV,M.V.BOKHOVKO, - A.A.VOEVODSKIY,V.M.TIMOKHOV,G.N.MANTUROV) -TITLE NEUTRON RADIATIVE CAPTURE CROSS-SECTIONS MEASUREMENTS - FOR U-236 AND AU-197 IN THE ENERGY RANGE 3-420 KEV -REFERENCE (J,YK,1985,(2),44,1985) MAIN REFERENCRE. - . NUMERICAL DATA GIVEN FOR U-236 AND AU-197 - (J,AE,64,(2),152,198802) DATA CURVES ARE GIVEN -FACILITY (VDG) EG-1 PULSED VAN-DE-GRAAFF ACCELERATOR -METHOD (TOF) FLIGHT BASE IS 2.4 M AND 0.72 M -DETECTOR (GLASD,NAICR) FOR NEUTRON FLUX MONITORING -ANALYSIS METHOD OF THE SATURATED RESONANCE -MONITOR NO INFORMATION -CORRECTION CORRECTIONS ON THE NEUTRON BACKGROUND AND - ON GAMMA-RAY SELF-ABSORPTION WERE MADE +AUTHOR (L.E.Kazakov,V.N.Kononov,E.D.Poletaev,M.V.Bokhovko, + A.A.Voevodskiy,V.M.Timokhov,G.N.Manturov) +TITLE Neutron radiative capture cross-sections measurements + for U-236 and Au-197 in the energy range 3-420 keV +REFERENCE (J,YK,1985,(2),44,1985) Main reference . + . Numerical Data Given For U-236 and Au-197 + (J,AE,64,(2),152,198802) Data curves are given + (J,SJA,64,(2),182,1988) Engl.transl of J,AE,64,(2),152. + #doi:10.1007/BF01153735 +FACILITY (VDG) EG-1 pulsed Van-de-Graaff accelerator +INC-SOURCE (P-LI7) +DETECTOR (GLASD,NAICR) For neutron flux monitoring +ANALYSIS Method of the saturated resonance +CORRECTION Corrections on the neutron background and + on gamma-ray self-absorption were made ADD-RES (COMP,POT) -STATUS DATA ARE TAKEN FROM THE MAIN REFERENCE -HISTORY (19860616C) + + COMPILED AT THE CENTRE - CJD + + - (19901031A) TWO SUBENTS ADDED WITH TOTAL U-236 CS - TWO SUBENTS ADDED WITH STRENGTH FUNCTIONS - ONE AUTHOR NAME ADDED (G.N.MANTUROV). - KEYWORDS FROM SAN 001 TRANSFERRED TO OTHERS - (19981116U) CORRECTED AT CJD +HISTORY (19860616C) + + compiled at the centre - CJD + + + (19901031A) two subents added with total U-236 CS + Two Subents Added With Strength Functions + One author name added (G.N.Manturov). + Keywords from SAN 001 transferred to others + (19981116U) Corrected at CJD (20010319A) DATE is corrected -ENDBIB 24 + (20110630A) M.M. Upper -> lower case correction. + Ref. J,SJA,64,(2),182,1988 was added. + BIB information was added. Subent 008 was added. +ENDBIB 27 NOCOMMON 0 0 -ENDSUBENT 27 -SUBENT 40890002 20010319 20010718 20050926 0000 -BIB 6 14 -REACTION (92-U-236(N,G)92-U-237,,SIG,,AV) AVERAGED OVER ENERGY - INTERVAL GIVEN IN DATA SECTION -SAMPLE DIAMETER 40.MM, U-235 CONTENT IS 0.047 PERCENT, - THICKNESS 4.07E-3 ATOMS/B -DETECTOR (STANK) LIQUID SCINTILLATOR -MONITOR (3-LI-6(N,T)2-HE-4,,SIG) BELOW 100KEV - (5-B-10(N,A)3-LI-7,,SIG) ABOVE 100 KEV -ERR-ANALYS (ERR-1) ERROR DUE TO THE BACKGROUND SUBTRACTION - (ERR-2) ERROR DUE TO THE NORMALIZATION - (ERR-3) ERROR OF THE CROSS-SECTION RELATIVE ENERGY - DEPENDENCE OF THE MONITOR - (ERR-4) ERROR DUE TO THE CORRECTIONS -HISTORY (19981116T) .DATA COINCIDE WITH 88033003 - .REFERENCE MOVED TO SAN 001 -ENDBIB 14 +ENDSUBENT 30 +SUBENT 40890002 20100701 20111003 20110930 4153 +BIB 8 17 +REACTION (92-U-236(N,G)92-U-237,,SIG,,AV) Averaged over energy + interval given in data section +SAMPLE Diameter 40.mm, U-235 content is 0.047 % , + thickness 4.07E-3 atoms/b +DETECTOR (STANK) Liquid Scintillator +MONITOR (3-LI-6(N,T)2-HE-4,,SIG) Below 100 keV + (5-B-10(N,A)3-LI-7,,SIG) Above 100 keV +METHOD (TOF) Flight base is 2.4 m and 0.72 m . + Resolution 5.6 - 2 ns/m. +ERR-ANALYS (ERR-1) Error due to the background subtraction + (ERR-2) Error due to the normalization + (ERR-3) Error of the cross-section relative energy + dependence of the monitor + (ERR-4) Error due to the corrections +STATUS (TABLE) Table 3 of J,YK,1985,(2),44,1985. +HISTORY (19981116T) .Data coincide with 88033003 + .REFERENCE moved to SAN 001 +ENDBIB 17 NOCOMMON 0 0 DATA 9 57 EN-MIN EN-MAX DATA ERR-T ERR-S ERR-1 @@ -166,23 +172,28 @@ PER-CENT PER-CENT PER-CENT 400. 420. 185. 9. 1.1 0.5 2. ENDDATA 118 -ENDSUBENT 137 -SUBENT 40890003 20010319 20010718 20050926 0000 -BIB 6 13 -REACTION (79-AU-197(N,G)79-AU-198,,SIG,,AV) AVERAGED OVER - ENERGY INTERVAL GIVEN IN DATA SECTION -SAMPLE DISK WITH DIAMETER 40 MM, THICKNESS 4.58E-3 ATOMS/B -DETECTOR (STANK) LIQUID SCINTILLATOR -MONITOR (3-LI-6(N,T)2-HE-4,,SIG) BELOW 100KEV - (5-B-10(N,A)3-LI-7,,SIG) ABOVE 100KEV -ERR-ANALYS (ERR-1) ERROR DUE TO THE BACKGROUND SUBTRACTION - (ERR-2) ERROR DUE TO THE NORMALIZATION - (ERR-3) ERROR OF THE CROSS-SECTION RELATIVE ENERGY - DEPENDENCE OF THE MONITORS - (ERR-4) ERROR DUE TO THE CORRECTIONS -HISTORY (19981116T) .DATA COINCIDE WITH 88033002 - .REFERENCE MOVED TO SAN 001 -ENDBIB 13 +ENDSUBENT 140 +SUBENT 40890003 20100701 20111003 20110930 4153 +BIB 8 18 +REACTION (79-AU-197(N,G)79-AU-198,,SIG,,AV) Averaged over + energy interval given in DATA section +SAMPLE Disk with diameter 40 mm, thickness 4.58e-3 atoms/b +DETECTOR (STANK) Liquid scintillator +MONITOR (3-LI-6(N,T)2-HE-4,,SIG) Below 100 keV + (5-B-10(N,A)3-LI-7,,SIG) Above 100 keV +METHOD (TOF) Flight base is 2.4 m and 0.72 m . + Resolution 5.6 - 2 ns/m. +ERR-ANALYS (ERR-1) Error due to the background subtraction + (ERR-2) Error due to the normalization + (ERR-3) Error of the cross-section relative energy + dependence of the monitors + (ERR-4) Error due to the corrections + (ERR-S) Statistical error. + (ERR-T) Total error. +STATUS (TABLE) Table 3 of J,YK,1985,(2),44,1985. +HISTORY (19981116T) .Data coincide with 88033002 + .REFERENCE moved to SAN 001 +ENDBIB 18 NOCOMMON 0 0 DATA 9 57 EN-MIN EN-MAX DATA ERR-T ERR-S ERR-1 @@ -304,24 +315,28 @@ PER-CENT PER-CENT PER-CENT 400. 420. 151. 6. 1.0 0.5 2. ENDDATA 118 -ENDSUBENT 136 -SUBENT 40890004 20010319 20010718 20050926 0000 -BIB 6 7 -REACTION (92-U-236(N,TOT),,SIG,,RAW) TRANSMISSION -DETECTOR (GLASD) LI-6 GLASS DETECTOR -MONITOR NO INFORMATION -ERR-ANALYS (ERR-T) TOTAL ERROR -STATUS (APRVD) NUMERICAL DATA ARE OBTAINED FROM KAZAKOV, - 901030 -HISTORY (19981116U) REFERENCE MOVED TO SAN 001 -ENDBIB 7 +ENDSUBENT 141 +SUBENT 40890004 20100701 20111003 20110930 4153 +BIB 6 11 +REACTION (92-U-236(N,TOT),,TRN) Transmission +DETECTOR (GLASD) Li-6 glass detector +METHOD (TOF) Flight base is 0.51m and 2.2 m . + Resolution 8.- 2.3 ns/m. +ERR-ANALYS (DATA-ERR) Total error +STATUS (TABLE) Numerical data are obtained from Kazakov, + (APRVD) 1990-10-30 +HISTORY (19901030R) Data received. + (19981116U) REFERENCE moved to SAN 001 + (20110630A) M.M. SIG,,RAW -> TRN. + ERR-T -> DATA-ERR according to now-day rules. +ENDBIB 11 COMMON 1 3 THICKNESS ATOMS/B 4.07E-03 ENDCOMMON 3 DATA 4 18 -EN-MIN EN-MAX DATA ERR-T +EN-MIN EN-MAX DATA DATA-ERR KEV KEV NO-DIM PER-CENT 18. 22. 0.915 1.3 22. 26. 0.913 @@ -342,17 +357,21 @@ KEV KEV NO-DIM PER-CENT 620. 660. 0.934 660. 700. 0.935 0.6 ENDDATA 20 -ENDSUBENT 36 -SUBENT 40890005 20010319 20010718 20050926 0000 -BIB 6 7 -REACTION (92-U-236(N,TOT),,SIG,,RAW) TRANSMISSION -DETECTOR (GLASD) LI-6 GLASS DETECTOR -MONITOR NO INFORMATION -ERR-ANALYS (ERR-T) TOTAL ERROR -STATUS (APRVD) NUMERICAL DATA ARE OBTAINED FROM KAZAKOV, - 901030 -HISTORY (19981116U) REFERENCE MOVED TO SAN 001 -ENDBIB 7 +ENDSUBENT 40 +SUBENT 40890005 20100701 20111003 20110930 4153 +BIB 6 11 +REACTION (92-U-236(N,TOT),,TRN) Transmission +DETECTOR (GLASD) Li-6 Glass Detector +METHOD (TOF) Flight base is 0.51m and 2.2 m . + Resolution 8.- 2.3 ns/m. +ERR-ANALYS (DATA-ERR) Total error +STATUS (TABLE) Numerical data are obtained from Kazakov, + (APRVD) 1990-10-30 +HISTORY (19901030R) Data received. + (19981116U) REFERENCE moved to SAN 001 + (20110630A) M.M. SIG,,RAW -> TRN. + ERR-T -> DATA-ERR according to now-day rules. +ENDBIB 11 COMMON 1 3 THICKNESS ATOMS/B @@ -382,16 +401,20 @@ KEV KEV NO-DIM PER-CENT 620. 660. 0.778 660. 700. 0.776 0.6 ENDDATA 22 -ENDSUBENT 38 -SUBENT 40890006 20010319 20010718 20050926 0000 -BIB 4 4 +ENDSUBENT 42 +SUBENT 40890006 20100701 20111003 20110930 4153 +BIB 6 8 REACTION (92-U-236(N,TOT),,STF) -ASSUMED (ASSUM,92-U-236(N,TOT),,STF) FOR MOMENTUM L=0 -ERR-ANALYS (DATA-ERR) NOT SPECIFIED -HISTORY (19981116U) REFERENCE MOVED TO SAN 001 -ENDBIB 4 +ASSUMED (ASSUM,92-U-236(N,TOT),,STF) For momentum L=0 +REL-REF (R,,G.Carraro+,J,NP/A,257,333,1976) + (R,,L.Mawissen+,C,75WASH,2,729,1975) + References for ASSUMED data. +ERR-ANALYS (DATA-ERR) Not Specified +STATUS (TABLE) Text, page 152, of J,AE,64,(2),152,1988 +HISTORY (19981116U) REFERENCE moved to SAN 001 +ENDBIB 8 COMMON 4 3 -EN-MIN EN-MAX ASSUM ASSUM-ERR +EN-RES-MIN EN-RES-MAX ASSUM ASSUM-ERR KEV KEV NO-DIM NO-DIM 10. 700. 1.0E-01 1.E-05 ENDCOMMON 3 @@ -401,16 +424,20 @@ NO-DIM NO-DIM NO-DIM 1. 2.4E-04 2.E-05 2. 2.8E-04 7.E-05 ENDDATA 4 -ENDSUBENT 17 -SUBENT 40890007 20010319 20010718 20050926 0000 -BIB 4 4 +ENDSUBENT 21 +SUBENT 40890007 20100701 20111003 20110930 4153 +BIB 6 8 REACTION (92-U-236(N,G),,STF) -ASSUMED (ASSUM,92-U-236(N,G),,STF) FOR MOMENTUM L=0 -ERR-ANALYS (DATA-ERR) NOT SPECIFIED -HISTORY (19981116U) REFERENCE MOVED TO SAN 001 -ENDBIB 4 +ASSUMED (ASSUM,92-U-236(N,G),,STF) For momentum L=0 +REL-REF (R,,G.Carraro+,J,NP/A,257,333,1976) + (R,,L.Mawissen+,C,75WASH,2,729,1975) + References for ASSUMED data. +ERR-ANALYS (DATA-ERR) Not specified +STATUS (TABLE) Text, page 152, of J,AE,64,(2),152,1988 +HISTORY (19981116U) REFERENCE moved to SAN 001 +ENDBIB 8 COMMON 4 3 -EN-MIN EN-MAX ASSUM ASSUM-ERR +EN-RES-MIN EN-RES-MAX ASSUM ASSUM-ERR KEV KEV NO-DIM NO-DIM 6. 420. 1.55E-03 1.5E-04 ENDCOMMON 3 @@ -420,5 +447,24 @@ NO-DIM NO-DIM NO-DIM 1. 1.35E-03 7.E-05 2. 1.40E-03 1.4E-04 ENDDATA 4 +ENDSUBENT 21 +SUBENT 40890008 20100701 20111003 20110930 4153 +BIB 4 4 +REACTION (92-U-236(N,EL)92-U-236,POT,RAD) +ERR-ANALYS (DATA-ERR) Not specified +STATUS (TABLE) Text, page 152, of J,AE,64,(2),152,1988 +HISTORY (20110630C) Subent was added. +ENDBIB 4 +COMMON 2 3 +EN-MIN EN-MAX +KEV KEV + 6. 420. +ENDCOMMON 3 +DATA 3 2 +MOMENTUM L DATA DATA-ERR +NO-DIM FERMI FERMI + 1. 10.15 0.2 + 2. 5.65 0.15 +ENDDATA 4 ENDSUBENT 17 -ENDENTRY 7 +ENDENTRY 8 diff --git a/exforall/409/40930.x4 b/exforall/409/40930.x4 index d47929915..634d92245 100644 --- a/exforall/409/40930.x4 +++ b/exforall/409/40930.x4 @@ -1,6 +1,6 @@ -ENTRY 40930 20100812 20101201 20101129 4150 -SUBENT 40930001 20100812 20101201 20101129 4150 -BIB 10 38 +ENTRY 40930 20110125 20111003 20110930 4153 +SUBENT 40930001 20110125 20111003 20110930 4153 +BIB 10 40 TITLE Prompt neutrons spectra from the thermal neutron fission of U-233, U-235, Pu-239 and spontaneous fission of Cf-252 in the secondary neutron energy @@ -9,10 +9,12 @@ AUTHOR (B.I.Starostov,V.N.Nefedov,A.A.Boykov) REFERENCE (J,YK,1985,(3),16,198509) Data given for CF-252, curves only for other elements (R,INDC(CCP)-293,19,1989) Engl. translation of J,YK. + (C,83KIEV,2,290,1983) First author B.I.Starostov. + Details of measurement by plastic scintillator. INSTITUTE (4RUSNIR) METHOD (TOF) DETECTOR (IOCH) 4 Ionization Chambers containing pure methane - under 1.E+5 Pa peruser, fission fragment registration + under 1.E+5 Pa pressure, fission fragment registration efficiency - 99%(Cf-252),98%(U-233-235,Pu-239). (SCIN) 3 scintillation detectors: 1) FEU-71 + Anthracene Crystal of 1.8cm diameter and @@ -24,9 +26,9 @@ DETECTOR (IOCH) 4 Ionization Chambers containing pure methane 3)FEU-63+ plastic of 20cm diameter and 12cm height, set for 611cm TOF length and 3-12MeV energy interval For 2nd measurement cycle in 0.01-5MeV energy region: - gas csint. fis.fragments detectors, + gas scint. fis.fragments detectors, ionization chambers with U-235 layers, - gas csint.-ioniz. detector with U-235 metallic + gas scint.-ioniz. detector with U-235 metallic radiator. For Cf-252 - ionization chamber of 65g mass , contained U-235 8 layers. @@ -39,18 +41,31 @@ HISTORY (19870831C) Compiled at the CJD BIB and COMMON information was added. ERR-ANALYS (ERR-T) Total errors . (ERR-1) Error of registration efficiency. -ENDBIB 38 +ENDBIB 40 COMMON 1 3 ERR-1 PER-CENT 2.5 ENDCOMMON 3 -ENDSUBENT 45 -SUBENT 40930002 20100812 20101201 20101129 4150 -BIB 4 17 -REACTION (98-CF-252(0,F),PR,NU/DE,,MXD) +ENDSUBENT 47 +SUBENT 40930002 20110125 20111003 20110930 4153 +BIB 6 32 +REACTION (98-CF-252(0,F),PR,NU/DE,,MXD,DERIV) Relative to the Maxwell spectrum with temperature 1.42 MeV +ANALYSIS Cf-252 spectrum was derived from data of this + experiment and other works (REL-REFs) as weighted + average. +REL-REF (R,,B.I.Starostov+,J,YK,1980,(2/37),3,1980) Data and + method of averaging. + (R,,M.V.Blinov+,C,80KIEV,3,109,1980) + (R,,O.I.Batenkov+,R,INDC(NDS)-146,161,1983) + (R,,W.P.Poenitz+,R,INDC(NDS)-146,175,1983) + (R,,A.Lajtai+,R,INDC(NDS)-146,175,1983) + (R,,H.Klein,R,INDC(NDS)-146,191,1983) + (R,,H.Maerten+,R,INDC(NDS)-146,195,1983) + (R,,V.I.Bol'shov+,J,YK,1981,(3/42),43,1981) + (R,,J.W.Boldeman+,J,ANS,32,733,1979) STATUS (TABLE) Data are taken from Table 4 of J,YK. (COREL,40874003) Data in this Subent cover the whole (COREL,40874004) energy range in difference to Subents @@ -65,7 +80,9 @@ HISTORY (19990311A) REACTION value is given explicitly as (98-CF-252(0,F),PR,DE,N,,CALC)) -> (98-CF-252(0,F),PR,NU/DE,,MXD). E-DN -> KT-NRM. E-NM -> E. -ENDBIB 17 + (20110125A) DERIV in REACTION, + ANALYSIS, REL-REF were added. +ENDBIB 32 COMMON 1 3 KT-NRM MEV @@ -95,7 +112,7 @@ MEV MEV NO-DIM PER-CENT NO-DIM 1.340E-01 3.0 E-03 1.010E-00 2.5 1.440E-01 3.0 E-03 1.018E-00 2.5 1.550E-01 3.0 E-03 9.99 E-01 2.5 - 1.660E-01 3.0 E-03 9.83 E-00 2.5 + 1.660E-01 3.0 E-03 9.83 E-01 2.5 1.780E-01 3.0 E-03 9.70 E-01 2.5 1.940E-01 4.0 E-03 9.62 E-01 2.5 2.070E-01 4.0 E-03 9.64 E-01 2.5 @@ -118,39 +135,39 @@ MEV MEV NO-DIM PER-CENT NO-DIM 8.68 E-01 9.0 E-03 9.78 E-01 2. 9.06 E-01 1.1 E-02 1.000E-00 2. 1.002E-00 2.8 E-02 9.96 E-01 2. - 1.050E-00 2.8 E-02 1.002E-01 2. - 1.170E-00 2.8 E-02 1.011E-01 2. - 1.260E-00 2.9 E-02 1.023E-01 3. - 1.353E-00 3.5 E-02 1.028E-01 2.5 - 1.480E-00 2.9 E-02 1.044E-01 2.5 - 1.640E-00 2.6 E-02 1.026E-01 2.5 - 1.760E-00 2.5 E-02 1.020E-01 2.5 - 1.836E-00 2.6 E-02 1.027E-01 2. - 1.990E-00 3.0 E-02 1.024E-01 2. - 2.123E-00 3.1 E-02 1.023E-01 2. - 2.216E-00 3.1 E-02 1.027E-01 1.5 - 2.314E-00 3.1 E-02 1.024E-01 1.5 - 2.400E-00 3.1 E-02 1.030E-01 1.5 - 2.537E-00 3.8 E-02 1.034E-01 2. - 2.662E-00 3.3 E-02 1.030E-01 2.2 - 2.772E-00 3.0 E-02 1.034E-01 2.5 - 2.875E-00 4.1 E-02 1.026E-01 2.6 - 2.964E-00 3.1 E-02 1.034E-01 2.2 - 3.151E-00 3.4 E-02 1.020E-01 2. - 3.305E-00 3.3 E-02 1.024E-01 2.5 - 3.408E-00 6.2 E-02 1.015E-01 2.3 - 3.537E-00 6.2 E-02 1.015E-01 2.3 - 3.629E-00 6.8 E-02 1.014E-01 2.3 - 3.748E-00 6.8 E-02 1.014E-01 2.3 - 3.938E-00 6.2 E-02 1.017E-01 2.3 - 4.155E-00 6.2 E-02 1.015E-01 2.5 - 4.268E-00 6.2 E-02 1.015E-01 2.5 - 4.398E-00 6.5 E-02 1.017E-01 2.3 - 4.582E-00 6.5 E-02 1.015E-01 2.5 - 4.777E-00 6.5 E-02 1.015E-01 2. - 4.986E-00 6.5 E-02 1.013E-01 2. - 5.208E-00 6.5 E-02 1.018E-01 2. - 5.446E-00 6.5 E-02 1.011E-01 3. + 1.050E-00 2.8 E-02 1.002E-00 2. + 1.170E-00 2.8 E-02 1.011E-00 2. + 1.260E-00 2.9 E-02 1.023E-00 3. + 1.353E-00 3.5 E-02 1.028E-00 2.5 + 1.480E-00 2.9 E-02 1.044E-00 2.5 + 1.640E-00 2.6 E-02 1.026E-00 2.5 + 1.760E-00 2.5 E-02 1.020E-00 2.5 + 1.836E-00 2.6 E-02 1.027E-00 2. + 1.990E-00 3.0 E-02 1.024E-00 2. + 2.123E-00 3.1 E-02 1.023E-00 2. + 2.216E-00 3.1 E-02 1.027E-00 1.5 + 2.314E-00 3.1 E-02 1.024E-00 1.5 + 2.400E-00 3.1 E-02 1.030E-00 1.5 + 2.537E-00 3.8 E-02 1.034E-00 2. + 2.662E-00 3.3 E-02 1.030E-00 2.2 + 2.772E-00 3.0 E-02 1.034E-00 2.5 + 2.875E-00 4.1 E-02 1.026E-00 2.6 + 2.964E-00 3.1 E-02 1.034E-00 2.2 + 3.151E-00 3.4 E-02 1.020E-00 2. + 3.305E-00 3.3 E-02 1.024E-00 2.5 + 3.408E-00 6.2 E-02 1.015E-00 2.3 + 3.537E-00 6.2 E-02 1.015E-00 2.3 + 3.629E-00 6.8 E-02 1.014E-00 2.3 + 3.748E-00 6.8 E-02 1.014E-00 2.3 + 3.938E-00 6.2 E-02 1.017E-00 2.3 + 4.155E-00 6.2 E-02 1.015E-00 2.5 + 4.268E-00 6.2 E-02 1.015E-00 2.5 + 4.398E-00 6.5 E-02 1.017E-00 2.3 + 4.582E-00 6.5 E-02 1.015E-00 2.5 + 4.777E-00 6.5 E-02 1.015E-00 2. + 4.986E-00 6.5 E-02 1.013E-00 2. + 5.208E-00 6.5 E-02 1.018E-00 2. + 5.446E-00 6.5 E-02 1.011E-00 3. 5.700E-00 6.5 E-02 9.99 E-01 4. 5.973E-00 6.5 E-02 9.93 E-01 4. 6.170E-00 1.5 E-01 9.89 E-01 4. @@ -185,15 +202,15 @@ MEV MEV NO-DIM PER-CENT NO-DIM 13.6 2. E-01 7.89 E-01 9. 15.4 3. E-01 7.72 E-01 10. ENDDATA 112 -ENDSUBENT 138 -SUBENT 40930003 20100812 20101201 20101129 4150 +ENDSUBENT 153 +SUBENT 40930003 20110125 20111003 20110930 4153 BIB 4 7 REACTION (98-CF-252(0,F)0-NN-1,PR,KE) Average neutron energy. ADD-RES T was defined from ratio =(3/2)T for Maxwell distribution as N(E)=C*(E**0.5)*exp(-E/T) to be 1.42MeV STATUS (TABLE) Text of ref.J,YK, page 21 . -HISTORY (20100812A) Corrected: ),PR,AKE,N -> 0-NN-1,PR,KE +HISTORY (20100812A) Corrected: ),PR,AKE,N -> )0-NN-1,PR,KE according to N.Otsuka opinion (NDS IAEA). ENDBIB 7 NOCOMMON 0 0 @@ -203,8 +220,8 @@ MEV MEV 2.134 .015 ENDDATA 3 ENDSUBENT 15 -SUBENT 40930004 20100812 20101201 20101129 4150 -BIB 7 23 +SUBENT 40930004 20110125 20111003 20110930 4153 +BIB 7 24 REACTION (92-U-233(N,F),PR,NU/DE,,MXD) Ratio to the Maxwell spectrum with temperature 1.34 MeV @@ -228,7 +245,8 @@ HISTORY (19990311A) Reaction value is given explicitly as (92-U-233(0,F),PR,NU/DE,,MXD). E-DN -> KT-NRM. EN-DUM-NM -> EN-DUMMY. Digitized data were added. -ENDBIB 23 + (20110125A) B -> NO-DIM +ENDBIB 24 COMMON 4 3 EN-DUMMY KT-NRM E-ERR-DIG ERR-DIG EV MEV PER-CENT NO-DIM @@ -236,7 +254,7 @@ EV MEV PER-CENT NO-DIM ENDCOMMON 3 DATA 4 100 E DATA DATA-ERR FLAG -MEV B B NO-DIM +MEV NO-DIM NO-DIM NO-DIM 0.020351 0.96077 0.14829 4. 0.029543 0.93849 0.10284 4. 0.043670 0.98383 0.73862E-01 4. @@ -338,8 +356,8 @@ MEV B B NO-DIM 9.2176 0.85380 3. 9.3697 0.88731 3. ENDDATA 102 -ENDSUBENT 134 -SUBENT 40930005 20100812 20101201 20101129 4150 +ENDSUBENT 135 +SUBENT 40930005 20110125 20111003 20110930 4153 BIB 6 10 REACTION (92-U-233(N,F)0-NN-1,PR,KE,,MXW) Average neutron energy. @@ -349,7 +367,7 @@ ADD-RES T was defined from ratio =(3/2)T for Maxwell distribution as N(E)=C*(E**0.5)*exp(-E/T) to be 1.34MeV STATUS (TABLE) Text of ref.J.YK, page 21 . HISTORY (20100812A) Corrected: - ),PR,AKE,N,MXW -> 0-NN-1,PR,KE,,MXW + ),PR,AKE,N,MXW -> )0-NN-1,PR,KE,,MXW according to N.Otsuka opinion (NDS IAEA). ENDBIB 10 NOCOMMON 0 0 @@ -359,8 +377,8 @@ EV MEV MEV 0.0253 2.015 .015 ENDDATA 3 ENDSUBENT 18 -SUBENT 40930006 20100812 20101201 20101129 4150 -BIB 7 23 +SUBENT 40930006 20110125 20111003 20110930 4153 +BIB 7 24 REACTION (92-U-235(N,F),PR,NU/DE,,MXD) Ratio to the Maxwell spectrum with temperature 1.313MeV @@ -384,15 +402,16 @@ HISTORY (19990311A) Reaction value is given explicitly as (92-U-235(0,F),PR,NU/DE,,MXD). E-DN -> KT-NRM. EN-DUM-NM -> EN-DUMMY. Digitized data were added. -ENDBIB 23 + (20110125A) B -> NO-DIM +ENDBIB 24 COMMON 4 3 EN-DUMMY KT-NRM E-ERR-DIG ERR-DIG EV MEV PER-CENT NO-DIM 0.0253 1.313 0.904E-02 0.770E-03 ENDCOMMON 3 DATA 4 126 -EN DATA DATA-ERR FLAG -MEV B B NO-DIM +E DATA DATA-ERR FLAG +MEV NO-DIM NO-DIM NO-DIM 0.021219 0.94102 0.14781 4. 0.030625 0.94144 0.10518 4. 0.043601 0.95665 0.75048E-01 4. @@ -520,8 +539,8 @@ MEV B B NO-DIM 9.6239 0.79189 3. 10.636 0.75091 3. ENDDATA 128 -ENDSUBENT 160 -SUBENT 40930007 20100812 20101201 20101129 4150 +ENDSUBENT 161 +SUBENT 40930007 20110125 20111003 20110930 4153 BIB 6 10 REACTION (92-U-235(N,F)0-NN-1,PR,KE,,MXW) Average neutron energy. @@ -529,9 +548,9 @@ INC-SPECT Thermal neutrons of the reactor FACILITY (REAC,4RUSNIR) CM-2 Reactor ADD-RES T was defined from ratio =(3/2)T for Maxwell distribution as N(E)=C*(E**0.5)*exp(-E/T)to be 1.313MeV -STATUS (TABLE) Text of ref.J.YK, page 21 . +STATUS (TABLE) Text of ref.J,YK, page 21 . HISTORY (20100812A) Corrected: - ),PR,AKE,N,MXW -> 0-NN-1,PR,KE,,MXW + ),PR,AKE,N,MXW -> )0-NN-1,PR,KE,,MXW according to N.Otsuka opinion (NDS IAEA). ENDBIB 10 NOCOMMON 0 0 @@ -541,8 +560,8 @@ EV MEV MEV 0.0253 1.970 .015 ENDDATA 3 ENDSUBENT 18 -SUBENT 40930008 20100812 20101201 20101129 4150 -BIB 7 22 +SUBENT 40930008 20110125 20111003 20110930 4153 +BIB 7 23 REACTION (94-PU-239(N,F),PR,NU/DE,,MXD) Ratio to the Maxwell spectrum with temperature 1.382 MeV @@ -565,15 +584,16 @@ HISTORY (19990311A) REACTION value is given explicitly as (94-PU-239(0,F),PR,NU/DE,,MXD). E-DN -> KT-NRM. EN-DUM-NM -> EN-DUMMY. Digitized data were added. -ENDBIB 22 + (20110125A) B -> NO-DIM, EN -> E. +ENDBIB 23 COMMON 4 3 EN-DUMMY KT-NRM E-ERR-DIG ERR-DIG EV MEV PER-CENT NO-DIM 0.0253 1.382 0.136E-01 0.990E-03 ENDCOMMON 3 DATA 4 139 -EN DATA DATA-ERR FLAG -MEV B B NO-DIM +E DATA DATA-ERR FLAG +MEV NO-DIM NO-DIM NO-DIM 0.020658 1.0264 0.14479 4. 0.030652 1.0153 0.12436 4. 0.044020 0.97927 0.73814E-01 4. @@ -714,8 +734,8 @@ MEV B B NO-DIM 10.551 0.75966 3. 11.287 0.71531 3. ENDDATA 141 -ENDSUBENT 172 -SUBENT 40930009 20100812 20101201 20101129 4150 +ENDSUBENT 173 +SUBENT 40930009 20110125 20111003 20110930 4153 BIB 6 10 REACTION (94-PU-239(N,F)0-NN-1,PR,KE,,MXW) Average neutron energy. @@ -725,7 +745,7 @@ ADD-RES T was defined from ratio =(3/2)T for Maxwell distribution as N(E)=C*(E**0.5)*exp(-E/T) to be 1.382. STATUS (TABLE) Text of ref.J,YK, page 21 . HISTORY (20100812A) Corrected: - ),PR,AKE,N,MXW -> 0-NN-1,PR,KE,,MXW + ),PR,AKE,N,MXW -> )0-NN-1,PR,KE,,MXW according to N.Otsuka opinion (NDS IAEA). ENDBIB 10 NOCOMMON 0 0 diff --git a/exforall/409/40958.x4 b/exforall/409/40958.x4 index 57e185681..1fafcd703 100644 --- a/exforall/409/40958.x4 +++ b/exforall/409/40958.x4 @@ -1,56 +1,80 @@ -ENTRY 40958 20010315 20010718 20050926 0000 -SUBENT 40958001 20010315 20010718 20050926 0000 -BIB 14 32 +ENTRY 40958 20110630 20111003 20110930 4153 +SUBENT 40958001 20110630 20111003 20110930 4153 +BIB 15 38 INSTITUTE (4RUSRI) REFERENCE (J,AE,64,(2),150,198802) -AUTHOR (YU.N.TROFIMOV) -TITLE U-236 NEUTRON RADIATION CROSS-SECTION IN THE ENERGY - RANGE 0.3 - 2.2 MEV -FACILITY (VDG) + (J,SJA,64,(2),179,1988) Engl.transl. of J,E,64,(2),150 + #doi:10.1007/BF01153734 +AUTHOR (Yu.N.Trofimov) +TITLE U-236 neutron radiation capture cross-section + for En=0.3-2.2 MeV +FACILITY (VDG,4RUSRI) +INC-SOURCE (P-T) METHOD (ACTIV) -DETECTOR (GELI) +DETECTOR (GELI) Ge(Li) detector of 38 cm**3 volume -to measure + energy and intensity of gammas. + Energy resolution 3.8 keV for Co-60 gamma-lines. + Spectrometer was calibrated by standard gamma-sources, + additionally by Np-237-,Pa-233. Efficiency dependence + was calibrated absolutely at 86.5, 312, 340, 415.8keV. MONITOR (79-AU-197(N,G)79-AU-198,,SIG) +MONIT-REF (,,R,IAEA-227,1983) DECAY-DATA (92-U-237,6.752D,DG,208.,0.224) -DECAY-MON (79-AU-198,2.694D,DG,411.8,0.9556) -CORRECTION CORRECTION WERE MADE ON THE NEUTRON SCATTERING ON THE - STRUCTURAL MATERIALS - 3 PC, ON THE NEUTRON FLUX NON- - STABILITY - UP TO 5 PC, ON THE GAMMA-RAYS SELF-ABSOR- - PTION - 1-TO-4 PERCENT -ERR-ANALYS (ERR-1) ERROR DUE TO THE NEUTRON SCATTERING ON STRUC- - TURAL MATERIALS - (ERR-2) ERROR CAUSED BY THE NEUTRON FLUX NON-STABILITY - (ERR-3) ERROR DUE TO THE GAMMA-RAYS SELF-ABSORPTION - (ERR-4) MAXIMAL ERROR CAUSED BY THE GAMMA-ACTIVITY - MEASUREMENT - (ERR-5) MAX ERROR OF THE DETECTOR EFFICIENCY - (ERR-6) MIN ERROR OF THE MONITOR REACTION - (ERR-7) MAX ERROR OF THE MONITOR REACTION - (ERR-8) ERROR OF THE GEOMETRY - (ERR-9) ERROR DUE TO THE ISOTOPIC PURITY OF THE - SAMPLE - (ERR-10) ERROR CAUSED BY THE U-236 SAMPLE WEIGHING - (ERR-11) ERROR CAUSED BY THE AU-197 SAMPLE WEIGHING -STATUS FROM THE TABLE GIVEN IN THE REFERENCE -HISTORY (19880729C) COMPILED AT THE CJD - (20010315A) DATE is corrected -ENDBIB 32 -COMMON 11 6 -ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 -ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 + HL=6.752+-0.002d. +REL-REF (R,,A.V.Bushuev+,J,YK,1982,(2),30,1982) + Reference for U-237 208-keV gamma line intensity. + (R,,C.Lederer+,B,LEDERER-7,,1978) + Reference for U-237 HL. +DECAY-MON (79-AU-198,2.6946D,DG,411.8,0.9556) + HL=2.6946+-0.0010 d. 0.9556 +- 0.0007. +CORRECTION Correction were made for the neutron scattering on the + structural materials - 3 %, for the neutron flux non- + stability - up to 5 %, for the gamma-rays self-absor- + ption - 1-to-4 % . +HISTORY (19880729C) Compiled at the CJD + (20010315A) Date is corrected + (20110630A) M.M. J,SJA,64,(2),179,1988 was added. + Upper -> lower case correction. + TITLE was corrected. BIB information was added. + ERR-ANALYS was corrected according to now-day rules + and moved in Subent 002. + ERR-7 -> MONIT-ERR. +ENDBIB 38 +NOCOMMON 0 0 +ENDSUBENT 41 +SUBENT 40958002 20110630 20111003 20110930 4153 +BIB 4 22 +REACTION (92-U-236(N,G)92-U-237,,SIG) +SAMPLE Uranium oxide powder, U-234 content is .001 % , + U-235 content is 0.047 % ,U-236 content is 99.845+- + .005 % , U-238 content is 0.107+-.002 % . + Placed between polyethylene foils of .08 mm thickness + U samples of 9.61+-0.19, 6.20+-0.12 mg, Au - 45 mg. +ERR-ANALYS (ERR-1) Error due to the neutron scattering on struc- + tural materials + (ERR-2) Error caused by the neutron flux non-stability + (ERR-3) Error due to the gamma-rays self-absorption + (ERR-4,1.,3.) Error of the gamma-activity measurement + (ERR-5,3.,4.) Error of the detector efficiency + (MONIT-ERR,6.,10.) Error of the monitor reaction + (ERR-8) Error of the geometry + (ERR-9) Error due to the isotopic purity of the + sample + (ERR-10) Error caused by the U-236 sample weighing + (ERR-11) Error caused by the Au-197 sample weighing + (ERR-T) Total error. +STATUS (TABLE) Table 2 of J,AE,64,(2),150,1988. + (COREL,41001042) Different samples. + (COREL,40975027) Different decay- data (intensity) +ENDBIB 22 +COMMON 7 6 +ERR-1 ERR-2 ERR-3 ERR-8 ERR-9 ERR-10 +ERR-11 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT -PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT - 1. .2 .5 3. 4. 6. - 10. 1.5 .005 2. 1. +PER-CENT + 1. 0.2 0.5 1.5 .005 2.0 + 1.0 ENDCOMMON 6 -ENDSUBENT 42 -SUBENT 40958002 20010315 20010718 20050926 0000 -BIB 2 4 -REACTION (92-U-236(N,G)92-U-237,,SIG) -SAMPLE URANIUM OXIDE POWDER, U-234 CONTENT IS .001 PC, - U-235 CONTENT IS 0.047 PC,U-236 CONTENT IS 99.845+- - .005 PC, U-238 CONTENT IS 0.107+-.002 PC -ENDBIB 4 -NOCOMMON 0 0 DATA 5 11 EN EN-RSL DATA ERR-T MONIT MEV MEV MB MB MB @@ -66,5 +90,5 @@ MEV MEV MB MB MB 2.00 .08 57. 7. 54. 2.20 .08 62. 8. 46. ENDDATA 13 -ENDSUBENT 22 +ENDSUBENT 47 ENDENTRY 2 diff --git a/exforall/409/40959.x4 b/exforall/409/40959.x4 index dbe1c3569..eb23998b3 100644 --- a/exforall/409/40959.x4 +++ b/exforall/409/40959.x4 @@ -1,33 +1,49 @@ -ENTRY 40959 20010315 20010718 20050926 0000 -SUBENT 40959001 20010315 20010718 20050926 0000 -BIB 10 17 +ENTRY 40959 20110802 20111003 20110930 4153 +SUBENT 40959001 20110802 20111003 20110930 4153 +BIB 11 23 INSTITUTE (4RUSKUR) -REFERENCE (J,YF,46,(5),1326,198711) MAIN REFERENCE - (J,PTE,1986,(6),33,1986) EXPERIMENTAL DETAILS - (J,YF,8,1086,1968) EXPERIMENTAL DETAILS -AUTHOR (V.M.MOROZOV,YU.G.ZUBOV,N.S.LEBEDEVA) -TITLE FORWARD ELASTIC NEUTRON SCATTERING CROSS-SECTION - ON URANIUM -INC-SOURCE (D-D) -DETECTOR (SCIN) SEVEN STILBENE DETECTORS FOR NEUTRON - DETECTION - (LONGC) LONG COUNTER FOR PROTON MONITORING +REFERENCE (J,YF,46,(5),1326,198711) Main Reference + (J,SNP,46,(5),778,1987) Engl.translation of J,YF,46 . + (J,PTE,1986,(6),33,1986) Exp. details only + First author Yu.G.Zubov. +REL-REF (M,40307012,G.V.Gorlov,J,YF,8,(6),1086,1968) + Method of measurement for 4.-5.34 MeV energy range. +AUTHOR (V.M.Morozov,Yu.G.Zubov,N.S.Lebedeva) +TITLE Forward elastic neutron scattering differential + cross-section on uranium +FACILITY (ACCEL,4RUSKUR) Electrostatic accelerator ESU-2.5 . +INC-SOURCE (D-D) Heavy water vapor and heavy water ice as targets +DETECTOR (SCIN) Seven stilbene detectors for neutron + detection + (LONGC) Long counter for proton monitoring MONITOR (82-PB-0(N,EL)82-PB-0,,DA) -ERR-ANALYS ERRORS ARE GENERALLY NOT SPECIFIED, TOTAL ERROR - CONTAINS ERROR OF STANDARD CROSS-SECTION -STATUS FROM THE DATA TABLES GIVEN IN THE REFERENCE -HISTORY (19880901C) COMPILED IN THE CJD +ERR-ANALYS (ERR-1) Error of normalization. +HISTORY (19880901C) Compiled in the CJD (20010315A) DATE is corrected -ENDBIB 17 -NOCOMMON 0 0 -ENDSUBENT 20 -SUBENT 40959002 20010315 20010718 20050926 0000 -BIB 1 1 + (20110802A) M.M. In Subent 007 : MEV -> KEV. + Upper -> lower case correction. + BIB information was added. + CALC -> DERIV. +ENDBIB 23 +COMMON 1 3 +ERR-1 +PER-CENT + 7. +ENDCOMMON 3 +ENDSUBENT 30 +SUBENT 40959002 20110802 20111003 20110930 4153 +BIB 6 7 REACTION (92-U-0(N,EL)92-U-0,,DA) -ENDBIB 1 +SAMPLE Natural uranium cylinder of 0.073 at/b thickness. +CORRECTION For multiple scattering, for backgrounds. +ERR-ANALYS (ERR-S) Statistical error. +STATUS (TABLE) Table 1 of J,YF,46,(5),1326,1987 +HISTORY (20110802A) M.M. ERR-T -> ERR-S according to text, + p.1327 of J,YF,46,(5),1326,1987 . +ENDBIB 7 NOCOMMON 0 0 DATA 5 8 -EN EN-RSL ANG DATA ERR-T +EN EN-RSL ANG DATA ERR-S MEV KEV ADEG B/SR B/SR 4.32 140. 3.5 8.80 .18 4.32 140. 6.5 8.12 .16 @@ -38,11 +54,12 @@ MEV KEV ADEG B/SR B/SR 5.34 140. 3.5 9.60 .19 5.34 140. 6.5 9.05 .18 ENDDATA 10 -ENDSUBENT 16 -SUBENT 40959003 20010315 20010718 20050926 0000 -BIB 1 1 +ENDSUBENT 22 +SUBENT 40959003 20110802 20111003 20110930 4153 +BIB 2 2 REACTION (92-U-235(N,EL)92-U-235,,DA) -ENDBIB 1 +STATUS (TABLE) Table 2 of J,YF,46,(5),1326,1987 +ENDBIB 2 NOCOMMON 0 0 DATA 4 20 EN ANG DATA ERR-T @@ -68,11 +85,12 @@ KEV ADEG B/SR B/SR 1926. 18. 2.81 .11 1926. 23. 2.03 .08 ENDDATA 22 -ENDSUBENT 28 -SUBENT 40959004 20010315 20010718 20050926 0000 -BIB 1 1 +ENDSUBENT 29 +SUBENT 40959004 20110802 20111003 20110930 4153 +BIB 2 2 REACTION (92-U-238(N,EL)92-U-238,,DA) -ENDBIB 1 +STATUS (TABLE) Table 3 of J,YF,46,(5),1326,1987 +ENDBIB 2 NOCOMMON 0 0 DATA 4 20 EN ANG DATA ERR-T @@ -98,38 +116,46 @@ KEV ADEG B/SR B/SR 1926. 18. 2.89 .09 1926. 23. 2.36 .07 ENDDATA 22 -ENDSUBENT 28 -SUBENT 40959005 20010315 20010718 20050926 0000 -BIB 3 5 -REACTION (92-U-0(N,EL)92-U-0,,DA,,,CALC) DATA OBTAINED BY THE - EXTRAPOLATION OF MEASURED SIGMAS TO THE ZERO ANGLE -ERR-ANALYS (+DATA-ERR) POSITIVE UNSYMMETRIC ERROR - (-DATA-ERR) NEGATIVE UNSYMMETRIC ERROR -STATUS (DEP,40959002) -ENDBIB 5 +ENDSUBENT 29 +SUBENT 40959005 20110802 20111003 20110930 4153 +BIB 5 12 +REACTION (92-U-0(N,EL)92-U-0,,DA,,,DERIV) +ANALYSIS Data were obtained by the visual extrapolation of the + measured data to zero angle. +ERR-ANALYS (+DATA-ERR) Positive unsymmetrical error + (-DATA-ERR) Negative unsymmetrical error + Error of extrapolation. +STATUS (DEP,40959002) See ANALYSIS. + (DEP,40307012) See FLAG. + (TABLE) Table 1 of J,YF,46,(5),1326,1987 +HISTORY (20110802) M.M. + Data at EN=4.00 MeV were moved in Subent 40307024 + as published in REL-REF of G.V.Gorlov+. +ENDBIB 12 COMMON 1 3 ANG ADEG 0. ENDCOMMON 3 -DATA 5 5 +DATA 5 4 EN EN-RSL DATA +DATA-ERR -DATA-ERR MEV KEV B/SR B/SR B/SR - 4.00 140. 7.43 .60 .60 4.32 140. 9.20 .20 .10 4.67 140. 9.08 .40 .10 5.00 140. 9.75 .10 .10 5.34 140. 9.85 .20 .10 -ENDDATA 7 -ENDSUBENT 21 -SUBENT 40959006 20010315 20010718 20050926 0000 -BIB 3 5 -REACTION (92-U-235(N,EL)92-U-235,,DA,,,CALC) DATA OBTAINED BY - THE EXTRAPOLATION OF THE MEASURED DATA TO ZERO ANGLE -ERR-ANALYS (+DATA-ERR) POSITIVE UNSYMMETRIC ERROR - (-DATA-ERR) NEGATIVE UNSYMMETRIC ERROR -STATUS (DEP,40959003) -ENDBIB 5 +ENDDATA 6 +ENDSUBENT 27 +SUBENT 40959006 20110802 20111003 20110930 4153 +BIB 4 7 +REACTION (92-U-235(N,EL)92-U-235,,DA,,,DERIV) +ANALYSIS Data were obtained by the visual extrapolation of the + measured data to zero angle. +ERR-ANALYS (+DATA-ERR) Positive unsymmetrical error + (-DATA-ERR) Negative unsymmetrical error +STATUS (DEP,40959003) See ANALYSIS. + (TABLE) Table 2 of J,YF,46,(5),1326,1987 +ENDBIB 7 COMMON 3 3 EN-ERR EN-RSL ANG KEV KEV ADEG @@ -144,15 +170,17 @@ KEV B/SR B/SR B/SR 1848. 3.30 .10 .10 1926. 3.80 .10 .10 ENDDATA 7 -ENDSUBENT 21 -SUBENT 40959007 20010315 20010718 20050926 0000 -BIB 3 5 -REACTION (92-U-238(N,EL)92-U-238,,DA,,,CALC) DATA OBTAINED BY - THE EXTRAPOLATION OF THE MEASURED DATA TO ZERO ANGLE -ERR-ANALYS (+DATA-ERR) POSITIVE UNSYMMETRIC ERROR - (-DATA-ERR) NEGATIVE UNSYMMETRIC ERROR -STATUS (DEP,40959004) -ENDBIB 5 +ENDSUBENT 23 +SUBENT 40959007 20110802 20111003 20110930 4153 +BIB 4 7 +REACTION (92-U-238(N,EL)92-U-238,,DA,,,DERIV) +ANALYSIS Data were obtained by the visual extrapolation of the + measured data to zero angle. +ERR-ANALYS (+DATA-ERR) Positive unsymmetrical error + (-DATA-ERR) Negative unsymmetrical error +STATUS (DEP,40959004) See ANALYSIS. + (TABLE) Table 3 of J,YF,46,(5),1326,1987 +ENDBIB 7 COMMON 3 3 EN-ERR EN-RSL ANG KEV KEV ADEG @@ -160,21 +188,22 @@ KEV KEV ADEG ENDCOMMON 3 DATA 4 5 EN DATA +DATA-ERR -DATA-ERR -MEV B/SR B/SR B/SR +KEV B/SR B/SR B/SR 1620. 3.65 .10 .20 1696. 3.25 .10 .10 1771. 3.29 .10 .10 1848. 3.45 .10 .10 1926. 3.75 .10 .10 ENDDATA 7 -ENDSUBENT 21 -SUBENT 40959008 20010315 20010718 20050926 0000 -BIB 2 4 -REACTION (92-U-235(N,EL)92-U-235,,AMP,,FCT) DATA IS EQUAL TO - THE IMAGINARY PART OF THE SCATTERING AMPLITUDE AT - ZERO ANGLE WHICH IS K*SIGMA(TOT)/4PI +ENDSUBENT 23 +SUBENT 40959008 20110802 20111003 20110930 4153 +BIB 2 5 +REACTION (92-U-235(N,EL)92-U-235,,AMP,,FCT) DATA is equal to + the imaginary part of the scattering amplitude at + zero angle which IS K*SIGMA(TOT)/4PI STATUS (DEP,40959006) -ENDBIB 4 + (TABLE) Table 2 of J,YF,46,(5),1326,1987 +ENDBIB 5 COMMON 2 3 EN-ERR EN-RSL KEV KEV @@ -189,37 +218,40 @@ KEV CM CM 1848. 1.66E-12 3.E-14 1926. 1.72E-12 3.E-14 ENDDATA 7 -ENDSUBENT 20 -SUBENT 40959009 20010315 20010718 20050926 0000 -BIB 3 5 -REACTION (92-U-0(N,EL)92-U-0,,AMP,,FCT) DATA IS EQUAL TO - THE IMAGINARY PART OF THE SCATTERING AMPLITUDE AT - ZERO ANGLE WHICH IS EQUAL K*SIGMA(TOT)/4PI -FLAG (1.) DATUM WAS PUBLISHED IN REFERENCE TWO +ENDSUBENT 21 +SUBENT 40959009 20110802 20111003 20110930 4153 +BIB 3 8 +REACTION (92-U-0(N,EL)92-U-0,,AMP,,FCT) DATA is equal to + the imaginary part of the scattering amplitude at + zero angle which is equal K*SIGMA(TOT)/4PI STATUS (DEP,40959005) -ENDBIB 5 + (TABLE) Table 1 of J,YF,46,(5),1326,1987 +HISTORY (20110802) M.M. + Data at EN=4.00 MeV were moved in Subent 40307025 + as published in REL-REF of G.V.Gorlov+. +ENDBIB 8 COMMON 1 3 EN-RSL KEV 140. ENDCOMMON 3 -DATA 4 5 -EN DATA DATA-ERR FLAG -MEV CM CM NO-DIM - 4.00 2.71E-12 4.E-14 1. +DATA 3 4 +EN DATA DATA-ERR +MEV CM CM 4.32 2.83E-12 4.E-14 4.67 2.88E-12 4.E-14 5.00 2.93E-12 4.E-14 5.34 3.03E-12 4.E-14 -ENDDATA 7 -ENDSUBENT 21 -SUBENT 40959010 20010315 20010718 20050926 0000 -BIB 2 4 -REACTION (92-U-238(N,EL)92-U-238,,AMP,,FCT) DATA IS EQUAL TO - THE IMAGINARY PART OF THE SCATTERING AMPLITUDE AT - ZERO ANGLE WHICH IS EQUAL K*SIGMA(TOT)/4PI -STATUS (DEP,40959006) -ENDBIB 4 +ENDDATA 6 +ENDSUBENT 23 +SUBENT 40959010 20110802 20111003 20110930 4153 +BIB 2 5 +REACTION (92-U-238(N,EL)92-U-238,,AMP,,FCT) DATA is equal to + the imaginary part of the scattering amplitude at + zero angle which is equal K*SIGMA(TOT)/4PI +STATUS (DEP,40959007) + (TABLE) Table 3 of J,YF,46,(5),1326,1987 +ENDBIB 5 COMMON 2 3 EN-ERR EN-RSL KEV KEV @@ -234,5 +266,5 @@ KEV CM CM 1848. 1.74E-12 3.E-14 1926. 1.79E-12 3.E-14 ENDDATA 7 -ENDSUBENT 20 +ENDSUBENT 21 ENDENTRY 10 diff --git a/exforall/409/40968.x4 b/exforall/409/40968.x4 index b3a08a77f..0c29c7b7b 100644 --- a/exforall/409/40968.x4 +++ b/exforall/409/40968.x4 @@ -1,68 +1,78 @@ -ENTRY 40968 20030729 20050926 0000 -SUBENT 40968001 20030729 20050926 0000 -BIB 13 41 -TITLE AU-197 NEUTRON RADIATION CAPTURE CROSS-SECTION. - SYSTEMATIC ERROR ANALYSIS IN THE ACTIVATION METHOD -AUTHOR (A.N.DAVLETSHIN,V.N.KORYTCHENKO,A.O.TIPUNKOV, - S.V.TIKHONOV,V.A.TOLSTIKOV) +ENTRY 40968 20110720 20111003 20110930 4153 +SUBENT 40968001 20110720 20111003 20110930 4153 +BIB 13 43 +TITLE Cross section for radiative capture of neutrons by + Au-197. An analysis of sources of systematic errors in + measurement of activation. +AUTHOR (A.N.Davletshin,V.N.Korytchenko,A.O.Tipunkov, + S.V.Tikhonov,V.A.Tolstikov) INSTITUTE (4RUSFEI) -REFERENCE (J,AE,65,(5),343,198810) DATA TABLE IS GIVEN - (J,AE,58,(3),183,1985) ERROR STRUCTURE IS GIVEN -FACILITY (VDG) CASCADE GENERATOR +REFERENCE (J,AE,65,(5),343,198810) Data table is given + (J,AE,58,(3),183,1985) Error structure is given + Au-197 prelim.data. + Also U-236,Np-237 prelim data - see ENTRY 40969. + (J,SJA,65,(5),913,1988) Engl.translation of J,AE,65 . + #doi:10.1007/BF01121251 + (J,SJA,58,(3),216,1985) Engl.translation of J,AE,58 . + #doi:10.1007/BF01125358 +FACILITY (VDG,4RUSFEI) Cascade Generator INC-SOURCE (P-T,P-LI7) DECAY-DATA (79-AU-198-G,2.7D,DG,142.) -DETECTOR (GELI) -STATUS (APRVD) APPROUVED BY THE AUTHORS (TIKHONOV) AND - TOLSTIKOV). DATA IN THE TABLE ARE CORRECTED - 881212 -HISTORY (19890203C) COMPILED AT THE CJD +DETECTOR (GELI) Ge(Li) gamma-spectrometer to measure the + Au sample induced activity. +STATUS (APRVD) Approved by the authors (Tikhonov) and + Tolstikov). Data in the table are corrected + 1988-12-12 + (COREL,40969001) Data for Np-237,U-236. +HISTORY (19890203C) Compiled at the CJD (20030729A) DATE is corrected -CORRECTION THOROUGH INVESTIGATION OF SYSTEMATIC ERRORS WAS MADE - AND CORRESPONDING CORRECTIONS IN EARLIER RESULTS - INTRODUCED -METHOD (ACTIV) ACTIVATION -ERR-ANALYS (ERR-T) TOTAL ERROR IS SQUARE ROOT OF THE QUADRATIC - SUM OF ALL THE ERRORS - (ERR-1) ERROR DUE TO THE ACTIVE NUCLEI NUMBER - UNCERTAINTY - (ERR-2) ERROR DUE TO THE GE-LI DETECTOR EFFICIENCY - UNCERTAINTY - (ERR-3) MINIMUM ERROR DUE TO THE SCATTERED NEUTRON - CORRECTION UNCERTAINTY - (ERR-4) MAXIMUM ERROR DUE TO THE SCATTERED NEUTRON - CORRECTION UNCERTAINTY - (ERR-5) ERROR DUE TO THE UNCERTAINTY OF THE NUMBER - OF INTERACTIONS IN THE HYDROGEN COUNTER - (ERR-6) ERROR DUE TO THE UNTERTAINTY OF THE NUMBER - OF HYDROGEN ATOMS IN THE PROP-COUNTER - (ERR-7) ERROR DUE TO THE NUMBER OF ATOMS IN A SAMPLE - OF GOLD - (ERR-8) ERROR DUE TO THE COUNTER GEOMETRICAL FACTOR - CORRECTION - (ERR-9) ERROR DUE TO THE SAMPLE GEOMETRICAL FACTOR - CORRECTION - (MONIT-ERR) ERROR OF THE (N,P) STANDARD CROSS-SECTION -ENDBIB 41 -COMMON 10 6 -ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 -ERR-7 ERR-8 ERR-9 MONIT-ERR -PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT + (20110720A) Upper -> lower case correction. + References of Engl.translations were added. + BIB information was added. + ERR-ANALYS was corrected. +CORRECTION Thorough investigation of systematic errors was made + and corresponding corrections in earlier results + introduced +METHOD (ACTIV) Activation +ERR-ANALYS (ERR-T) Total error is square root of the quadratic + sum of all errors + (ERR-1) Error due to the active nuclei number + uncertainty + (ERR-2) Error due to the Ge-Li detector efficiency + uncertainty + (ERR-7) Error due to the number of atoms in a sample + of gold + (ERR-9) Error due to the sample geometrical factor + correction +ENDBIB 43 +COMMON 4 3 +ERR-1 ERR-2 ERR-7 ERR-9 PER-CENT PER-CENT PER-CENT PER-CENT - 0.7 1.5 1.8 2.7 2.0 1.1 - 0.1 0.3 0.6 1.0 -ENDCOMMON 6 -ENDSUBENT 51 -SUBENT 40968002 20030729 20050926 0000 -BIB 4 7 + 0.7 1.5 0.1 0.6 +ENDCOMMON 3 +ENDSUBENT 50 +SUBENT 40968002 20110720 20111003 20110930 4153 +BIB 7 14 REACTION (79-AU-197(N,G)79-AU-198-G,(M),SIG) MONITOR (92-U-235(N,F),,SIG) -INC-SPECT EN GIVEN IN THE DATA TABLE IS THE AVERAGE ENERGY - OF THE NEUTRON BEAM AND EN-RSL IS SQUARE ROOT OF THE - SPECTRUM DISPERSION -FLAG (1.) DATA GIVEN IN THIS LINE ARE OBTAINED WITH THE - GAS-COOLED NEUTRON TARGET -ENDBIB 7 -NOCOMMON +INC-SPECT EN given in the DATA table is the average energy + of the neutron beam and EN-RSL is square root of the + spectrum dispersion +DETECTOR (FISCH) U-235 fission chamber. +FLAG (1.) Data given in this line are obtained with the + gas-cooled neutron target +ERR-ANALYS (MONIT-ERR) Error of the (N,F) standard cross-section + (ERR-3) Uncertainty due to correction for scattered + neutrons. + (ERR-4) Uncertainty of FF registration efficiency by + fission chamber. +STATUS (TABLE) Table of J,AE,65,(5),343,1988. +ENDBIB 14 +COMMON 3 3 +MONIT-ERR ERR-3 ERR-4 +PER-CENT PER-CENT PER-CENT + 3.5 1.5 2.0 +ENDCOMMON 3 DATA 6 11 EN EN-RSL DATA ERR-T MONIT FLAG KEV KEV B PER-CENT B NO-DIM @@ -78,18 +88,34 @@ KEV KEV B PER-CENT B NO-DIM 779.1 31. .090 5. 1. 780. 31. .094 5. 1.137 1. ENDDATA 13 -ENDSUBENT 25 -SUBENT 40968003 20030729 20050926 0000 -BIB 4 7 +ENDSUBENT 36 +SUBENT 40968003 20110720 20111003 20110930 4153 +BIB 7 19 REACTION (79-AU-197(N,G)79-AU-198,,SIG) MONITOR (1-H-1(N,EL)1-H-1,,SIG) -INC-SPECT ENERGY 'EN' GIVEN IN THE DATA TABLE IS THE AVERAGE - ONE OF THE NEUTRON BEAM SPECTRUM AND EN-RSL IS - SQUARE ROOT OF THE NEUTRON SPECTRUM DISPERSION -FLAG (1.) DATA GIVEN IN THIS LINE ARE OBTAINED WITH THE - HELP OF GAS-COOLED NEUTRON TARGET -ENDBIB 7 -NOCOMMON +INC-SPECT Energy 'EN' given in the DATA table is the average + one of the neutron beam spectrum and EN-RSL is + square root of the neutron spectrum dispersion +DETECTOR (PROPC) Cylindrical proportional counters filled by + helium or methane . +FLAG (1.) Data given in this line are obtained with the + help of gas-cooled neutron target +ERR-ANALYS (MONIT-ERR) Error of the (N,P) standard cross-section + (ERR-3,1.8,2.7) Error due to the scattered neutron + correction uncertainty + (ERR-5) Error due to the uncertainty of the number + of interactions in the hydrogen counter + (ERR-6) Error due to the uncertainty of the number + of hydrogen atoms in the prop-counter + (ERR-8) Error due to the counter geometrical factor + correction +STATUS (TABLE) Table of J,AE,65,(5),343,1988. +ENDBIB 19 +COMMON 4 3 +MONIT-ERR ERR-5 ERR-6 ERR-8 +PER-CENT PER-CENT PER-CENT PER-CENT + 1.0 2.0 1.1 0.3 +ENDCOMMON 3 DATA 6 40 EN EN-RSL DATA ERR-T MONIT FLAG KEV KEV B PER-CENT B NO-DIM @@ -134,5 +160,5 @@ KEV KEV B PER-CENT B NO-DIM 1192. 15. .072 4. 1389. 17. .068 4. ENDDATA 42 -ENDSUBENT 54 +ENDSUBENT 70 ENDENTRY 3 diff --git a/exforall/409/40969.x4 b/exforall/409/40969.x4 index b91f49fc7..4c5604c7a 100644 --- a/exforall/409/40969.x4 +++ b/exforall/409/40969.x4 @@ -1,56 +1,87 @@ -ENTRY 40969 20030729 20050926 0000 -SUBENT 40969001 20030729 20050926 0000 -BIB 12 23 -TITLE NEUTRON RADIATION CAPTURE CROSS-SECTIONS FOR U-236, - U-238, NP-237 MEASURED BY THE ACTIVATION METHOD -AUTHOR (N.N.BULEEVA,A.N.DAVLETSHIN,O.A.TIPUNKOV, - S.V.TIKHONOV,V.A.TOLSTIKOV) +ENTRY 40969 20110725 20111003 20110930 4153 +SUBENT 40969001 20110725 20111003 20110930 4153 +BIB 14 54 +TITLE Activation-measured radiative neutron-capture cross + sections for U-236, U-238, Np-237. +AUTHOR (N.N.Buleeva,A.N.Davletshin,O.A.Tipunkov, + S.V.Tikhonov,V.A.Tolstikov) INSTITUTE (4RUSFEI) -REFERENCE (J,AE,65,(6),348,198811) RENORMALIZED DATA ARE GIVEN -FACILITY (VDG) CASCADE GENERATOR -METHOD (ACTIV) -DETECTOR (GELI) +REFERENCE (J,AE,65,(5),348,198811) Renormalized data are given + (J,SJA,65,(5),920,1988) + #doi:10.1007/BF01121252 + Engl.translation of J,AE,65,(5),348,1988 . + (J,AE,58,(3),183,1985) Prelim. data for U-236,Np-237. + Also for Au-197 - see ENTRY 40968. + (J,SJA,58,(3),216,1985) Engl.translation of J,AE,58 . + #doi:10.1007/BF01125358 + (J,AE,48,(2),87,1980) Prelim.data for U-238, Au-197 + (J,SJA,48,(2),97,1980) Engl.translation of J,AE,48. + #doi:10.1007/BF01121282 +REL-REF (I,,A.N.Davletshin+,J,PTE,5,56,1980) + Proportional counter details. + (M,,A.N.Davletshin+,J,AE,65,(5),343,198810) + Error analysis method details. + (M,,A.N.Davletshin+,J,SJA,65,(5),913,1988) + Engl.translation of J,AE,65,(5),343 +FACILITY (VDG,4RUSFEI) Cascade generator +METHOD (ACTIV) Au sample and investigated sample were + irradiated simultaneously with H counter and U-235 + fission chamber. +DETECTOR (GELI) To measure induced activity. + (PROPC) Hydrogen proportional counter and + (FISCH) U-235 fission chamber - for neutron beam. INC-SOURCE (P-T,P-LI7) -INC-SPECT NEUTRON ENERGY GIVEN IN THE DATA TABLE IS THE AVERAGE - ENERGY OF THE NEUTRON BEAM ---AND ENERGY RESOLUTION - EN-RSL IS THE SQUARE ROOT OF THE SPECTRUM ENERGY - DISPERSION -ERR-ANALYS (ERR-T) TOTAL ERROR EQUAL TO THE SQUARE ROOT OF THE - QUADRATIC SUM OF ALL ERRORS - (ERR-8) ERROR OF THE BACKGROUND CORRECTION ON THE - SCATTERED NEUTRONS - (ERR-9) ERROR OF THE ACTIVATION CAUSED BY THE NEUTRONS - SCATTERED IN THE BACKWARD DIRECTION -STATUS (APRVD) TIKHONOV,TOLSTIKOV, (881212) -HISTORY (19890209C) COMPILED AT THE CJD +INC-SPECT Neutron energy given in the data table is the average + energy of the neutron beam ---and energy resolution + EN-RSL is the square root of the spectrum energy + dispersion +ERR-ANALYS (ERR-T) Total error equal to the square root of the + quadratic sum of all errors + (ERR-8) Error of the background correction on the + scattered neutrons + (ERR-9) Error of the activation caused by the neutrons + scattered in the backward direction +STATUS (APRVD) Tikhonov,Tolstikov, (1988-12-12) + (COREL,40968001) Data for Au-197. + (COREL,40604001) Prelim. Au-197, U-238 data were in + ENTRY 40604 . +COMMENT Of compiler M.M. It Tables MONITORs values are given + for more energy points, at different energy than + EN in DATA block. Because this ENTRY was approved by + two authors, these monitor values were not corrected. +HISTORY (19890209C) Compiled at the CJD (20030729A) DATE is corrected -ENDBIB 23 + (20110725A) Upper -> lower case correction. + Reference of Engl.translation was added. + BIB information was added. + COMMENT was added. +ENDBIB 54 COMMON 2 3 ERR-8 ERR-9 PER-CENT PER-CENT 1.5 2. ENDCOMMON 3 -ENDSUBENT 30 -SUBENT 40969002 20030729 20050926 0000 -BIB 6 13 +ENDSUBENT 61 +SUBENT 40969002 20110725 20111003 20110930 4153 +BIB 7 13 REACTION (92-U-236(N,G)92-U-237,,SIG) MONITOR (1-H-1(N,EL)1-H-1,,SIG) -MONIT-REF (,UTLEY,R,IAEA-227,1983) FULL NAME IS IAEA-TECDOC -FLAG (1.) DATA POINT GIVEN IN THIS LINE IS OBTAINED - WITH THE GAS-COOLED NEUTRON TARGET -ERR-ANALYS (ERR-1) ERROR DUE TO THE GAMMA-REGISTRATION EFFICIENCY - (ERR-2) MINIMUM ERROR CAUSED BY THE INDUCED ACTIVITY - (ERR-3) MAXIMUM ERROR CAUSED BY THE INDUCED ACTIVITY - (ERR-4) ERROR CAUSED BY THE NEUTRONS COUNTS UNCERTAINTY - IN THE HYDROGEN COUNTER - (ERR-5) MONITOR CROSS-SECTION ERROR -CORRECTION SCATTERED BACKGROUND NEUTRONS CORRECTIONS - MIN - 1.6 PC, MAX - 2.8 PC +MONIT-REF (,C.Utley,R,IAEA-227,1983) Full name is IAEA-TECDOC +FLAG (1.) Data point given in this line is obtained + with the gas-cooled neutron target +ERR-ANALYS (ERR-1) Error due to the gamma-registration efficiency + (ERR-2,0.4,1.1) Error caused by the induced activity + (ERR-4) Error caused by the neutrons counts uncertainty + in the hydrogen counter + (MONIT-ERR,0.7,0.9) MONITOR cross-section error +CORRECTION Scattered background neutrons corrections + MIN - 1.6 % , MAX - 2.8 %. +STATUS (TABLE) Table 1 of J,AE,65,(5),348,1988. ENDBIB 13 -COMMON 5 3 -ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 -PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT - 1.6 .4 1.1 2.8 0.9 +COMMON 2 3 +ERR-1 ERR-4 +PER-CENT PER-CENT + 1.6 2.8 ENDCOMMON 3 DATA 6 13 EN EN-RSL DATA ERR-T MONIT FLAG @@ -70,26 +101,29 @@ KEV KEV B PER-CENT B NO-DIM 1134. 21. .133 4. ENDDATA 15 ENDSUBENT 37 -SUBENT 40969003 20030729 20050926 0000 -BIB 5 13 +SUBENT 40969003 20110725 20111003 20110930 4153 +BIB 7 16 REACTION (92-U-236(N,G)92-U-237,,SIG) MONITOR (79-AU-197(N,G)79-AU-198,,SIG) -FLAG (1.) DATA POINT GIVEN IN THIS LINE IS OBTAINED - WITH THE GAS-COOLED NEUTRON TARGET -ERR-ANALYS (ERR-1) GAMMA-QUANTA REGISTRATION EFFICIENCY ERROR - FROM GOLD - (ERR-2) GAMMA-QUANTA FROM-U-236 REGISTRATION - EFFICIENCY ERROR - (ERR-3) GOLD-INDUCED ACTIVITY ERROR - MAX - (ERR-4) U-236-INDUCED ACTIVITY ERROR - MAX -CORRECTION BACKGROUND CORRECTION FOR SCATTERED NEUTRONS IN GOLD - - MIN=1.6 PC, MAX=2.7 PC. BACKGROUND CORRECTION FOR - SCATTERED NEUTRONS IN U-236 - MIN=1.7, MAX=2.7 PC -ENDBIB 13 -COMMON 4 3 -ERR-1 ERR-2 ERR-3 ERR-4 -PER-CENT PER-CENT PER-CENT PER-CENT - 1.5 1.6 .6 1.1 +MONIT-REF (,,3,ENDF/B-VI,,1990) + Preliminary results for ENDF/B-VI were used. +FLAG (1.) Data point given in this line is obtained + with the gas-cooled neutron target +ERR-ANALYS (ERR-1) Gamma-quanta registration efficiency error + from gold + (ERR-2) Gamma-quanta from-u-236 registration + efficiency error + (ERR-3,,0.6) Gold-induced Activity Error - Max + (ERR-4,,1.1) U-236-Induced Activity Error - Max +CORRECTION Background correction for scattered neutrons in gold + - MIN=1.6 % , MAX=2.7 % . Background correction for + scattered neutrons in U-236 - MIN=1.7, MAX=2.7 %. +STATUS (TABLE) Table 1 of J,AE,65,(5),348,1988. +ENDBIB 16 +COMMON 2 3 +ERR-1 ERR-2 +PER-CENT PER-CENT + 1.5 1.6 ENDCOMMON 3 DATA 6 16 EN EN-RSL DATA ERR-T MONIT FLAG @@ -111,26 +145,26 @@ KEV KEV B PER-CENT B NO-DIM 1133. 20. .122 4. .076 1134. 21. .125 4. .076 ENDDATA 18 -ENDSUBENT 40 -SUBENT 40969004 20030729 20050926 0000 -BIB 6 12 +ENDSUBENT 43 +SUBENT 40969004 20110725 20111003 20110930 4153 +BIB 7 12 REACTION (92-U-236(N,G)92-U-237,,SIG) MONITOR (92-U-235(N,F),,SIG) -MONIT-REF (,YANKOV,R,IAEA-227,1983) FULL NAME IS IAEA-TECDOC -FLAG (1.) DATA VALUE IS OBTAINE WITH THE GAS-COOLED - NEUTRON TARGET -CORRECTION CORRECTION FOR BACKGROUND SCATTERED NEUTRONS - MINIMAL - 1.7 PC, MAXIMAL - 2.7 PC -ERR-ANALYS (ERR-1) GAMMA-QUANTA REGISTRATION EFFICIENCY ERROR - (ERR-2) MINIMUM INDUCED-ACTIVITY ERROR - (ERR-3) MAXIMUM INDUCED-ACTIVITY ERROR - (ERR-4) FISSION-FRAGMENTS REGISTRATION ERROR - (ERR-5) MONITOR SIGMA ERROR +MONIT-REF (,G.Yankov,R,IAEA-227,1983) Full name is IAEA-TECDOC +FLAG (1.) Data value is obtained with the gas-cooled + neutron target +CORRECTION Correction for background scattered neutrons + minimal - 1.7 % , maximal - 2.7 % +ERR-ANALYS (ERR-1) Gamma-quanta registration efficiency error + (ERR-2,0.4,1.1) Induced-activity error + (ERR-4) Fission-fragments registration error + (MONIT-ERR) MONITOR sigma error +STATUS (TABLE) Table 1 of J,AE,65,(5),348,1988. ENDBIB 12 -COMMON 5 3 -ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 -PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT - 1.6 0.4 1.1 2.5 3.5 +COMMON 3 3 +ERR-1 ERR-4 MONIT-ERR +PER-CENT PER-CENT PER-CENT + 1.6 2.5 3.5 ENDCOMMON 3 DATA 6 5 EN EN-RSL DATA ERR-T MONIT FLAG @@ -142,26 +176,26 @@ KEV KEV B PER-CENT B NO-DIM 779. 31. .188 5.5 1.137 1. ENDDATA 7 ENDSUBENT 28 -SUBENT 40969005 20030729 20050926 0000 -BIB 6 13 +SUBENT 40969005 20110725 20111003 20110930 4153 +BIB 7 13 REACTION (92-U-238(N,G)92-U-239,,SIG) MONITOR (1-H-1(N,EL)1-H-1,,SIG) -MONIT-REF (,UTLLEY,R,IAEA-227,1983) FULL NAME IS IAEA-TECDOC -FLAG (1.) DATA POINT GIVEN IN THIS LINE IS OBTAINED - ON THE GAS-COOLED NEUTRON SOURCE -CORRECTION SCATTERED NEUTRONS BACKGROUND CORRECTIONS ARE - MINIMAL - 0.4 PC, MAXIMAL - 1.3 PC -ERR-ANALYS (ERR-1) GAMMA-QUANTA REGISTRATION EFFICIENCY ERROR - (ERR-2) MINIMUM INDUCED-ACTIVITY ERROR - (ERR-3) MAXIMUM INDUCED-ACTIVITY ERROR - (ERR-4) ERROR DUE TO THE NEUTRON COUNTS UNCERTAINTY - IN THE HYDROGEN COUNTER - (ERR-5) MONITOR CROSS-SECT. ERROR +MONIT-REF (,C.Utlley,R,IAEA-227,1983) Full name is IAEA-TECDOC +FLAG (1.) Data point given in this line is obtained + on the gas-cooled neutron source +CORRECTION Scattered neutrons background corrections are + minimal - 0.4 % , maximal - 1.3 %. +ERR-ANALYS (ERR-1) Gamma-quanta registration efficiency error + (ERR-2,0.4,1.3) Induced-activity error + (ERR-4) Error due to the neutron counts uncertainty + in the hydrogen counter + (MONIT-ERR,0.7,0.9) MONITOR cross-section error +STATUS (TABLE) Table 2 of J,AE,65,(5),348,1988. ENDBIB 13 -COMMON 5 3 -ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 -PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT - 2. 0.4 1.3 2.8 .9 +COMMON 2 3 +ERR-1 ERR-4 +PER-CENT PER-CENT + 2. 2.8 ENDCOMMON 3 DATA 6 17 EN EN-RSL DATA ERR-T MONIT FLAG @@ -185,28 +219,28 @@ KEV KEV B PER-CENT B NO-DIM 1391.1 19. .076 3.5 ENDDATA 19 ENDSUBENT 41 -SUBENT 40969006 20030729 20050926 0000 -BIB 5 15 +SUBENT 40969006 20110725 20111003 20110930 4153 +BIB 7 15 REACTION (92-U-238(N,G)92-U-239,,SIG) MONITOR (79-AU-197(N,G)79-AU-198,,SIG) -FLAG (1.) DATA OBTAINED WITH THE GAS-COOLED NEUTRON TARGET -CORRECTION CORRECTIONS FOR BACKGROUN SCATTERED NEUTRONS ARE - IN GOLD 1.6 PC MIN, 2.7 - IN GOLD 1.6 PC MIN, 2.7 PC MAX AND IN U-238 1.6 PC - MIN, 2.7 PC MAX -ERR-ANALYS (ERR-1) GAMMA-QUANTA REGISTRATION EFFICIENCY ERROR - IN GOLD - (ERR-2) MINIMUM INDUCED-ACTIVITY ERROR IN GOLD - (ERR-3) MAXIMUM INDUCED-ACTIVITY ERROR IN GOLD - (ERR-4) GAMMA-QUANTA REGISTRATION EFFICIENCY ERROR - IN U-238 - (ERR-5) MINIMUM URANIUM-238 INDUCED-ACTIVITY ERROR - (ERR-6) MAXIMUM URANIUM-238 INDUCED-ACTIVITY ERROR +MONIT-REF (,,3,ENDF/B-VI,,1990) + Preliminary results for ENDF/B-VI were used. +FLAG (1.) Data obtained with the gas-cooled neutron target +CORRECTION Corrections for background scattered neutrons are + in gold 1.6 % min, 2.7 % max and in U-238 1.6 % + min, 2.7 % max +ERR-ANALYS (ERR-1) Gamma-quanta registration efficiency error + in gold + (ERR-2,0.3,0.6) Induced-activity error in gold + (ERR-4) Gamma-quanta registration efficiency error + in U-238 + (ERR-5,0.4,1.3) Uranium-238 induced-activity error +STATUS (TABLE) Table 2 of J,AE,65,(5),348,1988. ENDBIB 15 -COMMON 6 3 -ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 -PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT - 1.5 .3 .6 2. .4 1.3 +COMMON 2 3 +ERR-1 ERR-4 +PER-CENT PER-CENT + 1.5 2. ENDCOMMON 3 DATA 6 2 EN EN-RSL DATA ERR-T MONIT FLAG @@ -215,24 +249,24 @@ KEV KEV B PER-CENT B NO-DIM 780. 31. .124 4.5 .093 1. ENDDATA 4 ENDSUBENT 28 -SUBENT 40969007 20030729 20050926 0000 -BIB 6 11 +SUBENT 40969007 20110725 20111003 20110930 4153 +BIB 7 11 REACTION (92-U-238(N,G)92-U-239,,SIG) MONITOR (92-U-235(N,F),,SIG) -MONIT-REF (,YANKOV,R,IAEA-227,1983) RIGHT NAME IS IAEA-TECDOC -FLAG (1.) DATA OBTAINED WITH THE GAS-COOLED NEUTRON TARGET -CORRECTION CORRECTIONS FOR BACKGROUND SCATTERED NEUTRONS IN - U-238 ARE MAX 2.7 PC, MIN 1.6PC -ERR-ANALYS (ERR-4) GAMMA REGISTRATION EFFICIENCY ERROR IN U-238 - (ERR-5) MINIMUM INDUCED-ACTIVITY ERROR IN U-238 - (ERR-6) MAXIMUM INDUCED-ACTIVITY ERROR IN U-238 - (ERR-7) UNCERTAINITY OF FISSION FRAGMENT REGISTRATION - ERROR +MONIT-REF (,G.Yankov,R,IAEA-227,1983) Right name is IAEA-TECDOC +FLAG (1.) Data obtained with the gas-cooled neutron target +CORRECTION Corrections for background scattered neutrons in + U-238 are max 2.7 % , min 1.6 %. +ERR-ANALYS (ERR-4) Gamma registration efficiency error in U-238 + (ERR-5,0.4,1.3) Induced-activity error in U-238 + (ERR-7) Uncertainty of fission fragment registration + error +STATUS (TABLE) Table 2 of J,AE,65,(5),348,1988. ENDBIB 11 -COMMON 4 3 -ERR-4 ERR-5 ERR-6 ERR-7 -PER-CENT PER-CENT PER-CENT PER-CENT - 2. .4 1.3 2.5 +COMMON 2 3 +ERR-4 ERR-7 +PER-CENT PER-CENT + 2. 2.5 ENDCOMMON 3 DATA 6 2 EN EN-RSL DATA ERR-T MONIT FLAG @@ -241,25 +275,25 @@ KEV KEV B PER-CENT B NO-DIM 780. 31. .125 5. .093 1. ENDDATA 4 ENDSUBENT 24 -SUBENT 40969008 20030729 20050926 0000 -BIB 6 12 +SUBENT 40969008 20110725 20111003 20110930 4153 +BIB 7 12 REACTION (93-NP-237(N,G)93-NP-238,,SIG) MONITOR (1-H-1(N,EL)1-H-1,,SIG) -MONIT-REF (,UTLLEY,R,IAEA-227,1983) -FLAG (1.) DATA OBTAINED WITH THE GAS-COOLEN NEUTRON TARGET -CORRECTION SCATTERED NEUTRONS BACKGROUND CORRECTIONS ARE - 1.8 PC MIN, 2.8 PC MAX -ERR-ANALYS (ERR-4) GAMMA REGISTRATION EFFICIENCY ERROR IN NP-237 - (ERR-5) MINIMUM INDUCED-ACTIVITY ERROR IN NP-237 - (ERR-6) MAXIMUM INDUCED-ACTIVITY ERROR IN NP-237 - (ERR-7) NEUTRON REGISTRATION UNCERTAINTY ERROR IN - NYDROGEN COUNTER. - (ERR-10) ADD ERR-10 +MONIT-REF (,C.Utlley,R,IAEA-227,1983) +FLAG (1.) Data obtained with the gas-cooled neutron target +CORRECTION Scattered neutrons background corrections are + 1.8 % min, 2.8 % max +ERR-ANALYS (ERR-4) Gamma registration efficiency error in NP-237 + (ERR-5,1.,2.4) Induced-activity error in Np-237 + (ERR-7) Neutron registration uncertainty error in + hydrogen counter. + (MONIT-ERR,0.7,0.9) MONITOR cross-section error +STATUS (TABLE) Table 3 of J,AE,65,(5),348,1988. ENDBIB 12 -COMMON 5 3 -ERR-4 ERR-5 ERR-6 ERR-7 ERR-10 -PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT - 2.5 1. 2.4 2.8 0.9 +COMMON 3 3 +ERR-4 ERR-7 MONIT-ERR +PER-CENT PER-CENT PER-CENT + 2.5 2.8 0.9 ENDCOMMON 3 DATA 6 13 EN EN-RSL DATA ERR-T MONIT FLAG @@ -279,25 +313,26 @@ KEV KEV B PER-CENT B NO-DIM 1142. 17. .094 5. ENDDATA 15 ENDSUBENT 36 -SUBENT 40969009 20030729 20050926 0000 -BIB 5 12 +SUBENT 40969009 20110725 20111003 20110930 4153 +BIB 7 13 REACTION (93-NP-237(N,G)93-NP-238,,SIG) MONITOR (79-AU-197(N,G)79-AU-198,,SIG) -FLAG (1.) DATA OBTAINED WITH THE GAS-COOLED NEUTRON TARGET -CORRECTION SCATTERED BACKGROUND NEUTRON CORRECTIONS IN GOLD - IS 1.6 PC MIN, 2.7 PC MAX. IN NP-237 1.8 PC MIN, - 2.8 PC MAX -ERR-ANALYS (ERR-1) GAMMA REGISTRATION EFFICIENCY ERROR IN GOLD - (ERR-2) MINIMUM INDUCED-ACTIVITY ERROR IN GOLD - (ERR-3) MAXIMUM INDUCED-ACTIVITY ERROR IN GOLD - (ERR-4) GAMMA REGISTRATION EFFICIENCY ERROR IN NP-238 - (ERR-5) MINIMUM INDUCED-ACTIVITY ERROR IN NP-238 - (ERR-6) MAXIMUM INDUCED-ACTIVITY ERROR IN NP-238 -ENDBIB 12 -COMMON 6 3 -ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 -PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT - 1.5 .3 .6 2.5 1. 2.4 +MONIT-REF (,,3,ENDF/B-VI,,1990) + Preliminary results for ENDF/B-VI were used. +FLAG (1.) Data obtained with the gas-cooled neutron target +CORRECTION Scattered background neutron corrections in gold + is 1.6 % min, 2.7 % max. In Np-237 1.8 % min, + 2.8 % max. +ERR-ANALYS (ERR-1) Gamma registration efficiency error in gold + (ERR-2,0.3,0.6) Induced-activity error in gold + (ERR-4) Gamma registration efficiency error in Np-238 + (ERR-5,1.,2.4) Induced-activity error in Np-238 +STATUS (TABLE) Table 3 of J,AE,65,(5),348,1988. +ENDBIB 13 +COMMON 4 3 +ERR-1 ERR-4 ERR-5 ERR-6 +PER-CENT PER-CENT PER-CENT PER-CENT + 1.5 2.5 1. 2.4 ENDCOMMON 3 DATA 6 17 EN EN-RSL DATA ERR-T MONIT FLAG @@ -320,25 +355,25 @@ KEV KEV B PER-CENT B NO-DIM 1042. 22. .098 4. .0790 1142. 17. .089 4. .0760 ENDDATA 19 -ENDSUBENT 40 -SUBENT 40969010 20030729 20050926 0000 -BIB 6 11 +ENDSUBENT 41 +SUBENT 40969010 20110725 20111003 20110930 4153 +BIB 7 11 REACTION (93-NP-237(N,G)93-NP-238,,SIG) MONITOR (92-U-235(N,F),,SIG) -MONIT-REF (,YANKOV,R,IAEA-227,1983) -FLAG (1.) DATA OBTAINED WITH THE GAS-COOLED NEUTRON TARGET -CORRECTION SCATTERED NEUTRONS BACKGROUND CORRECTIONS IN NP-237 - ARE 1.8 PC MIN, 2.8 PC MAX -ERR-ANALYS (ERR-4) GAMMA REGISTRATION EFFICIENCY ERROR IN NP - (ERR-5) MINIMUM INDUCED-ACTIVITY ERROR IN NP - (ERR-6) MAXIMUM INDUCED-ACTIVITY ERROR IN NP - (ERR-7) UNCERTAINTY OF U-235 FISSION-FRAGMENTS - REGISTRATION ERROR +MONIT-REF (,G.Yankov,R,IAEA-227,1983) +FLAG (1.) Data obtained with the gas-cooled neutron target +CORRECTION Scattered neutrons background corrections in Np-237 + are 1.8 % min, 2.8 % max . +ERR-ANALYS (ERR-4) Gamma registration efficiency error in Np + (ERR-5,1.,2.4) Induced-activity error in Np + (ERR-7) Uncertainty of U-235 fission-fragments + registration error +STATUS (TABLE) Table 3 of J,AE,65,(5),348,1988. ENDBIB 11 -COMMON 4 3 -ERR-4 ERR-5 ERR-6 ERR-7 -PER-CENT PER-CENT PER-CENT PER-CENT - 2.5 1. 2.4 2.5 +COMMON 2 3 +ERR-4 ERR-7 +PER-CENT PER-CENT + 2.5 2.5 ENDCOMMON 3 DATA 6 3 EN EN-RSL DATA ERR-T MONIT FLAG @@ -348,14 +383,16 @@ KEV KEV B PER-CENT B NO-DIM 763. 34. .210 6. 1.137 1. ENDDATA 5 ENDSUBENT 25 -SUBENT 40969011 20030729 20050926 0000 -BIB 4 4 +SUBENT 40969011 20110725 20111003 20110930 4153 +BIB 6 6 REACTION (92-U-235(N,F),,SIG) -FLAG (1.) DATA OBTAINED WITH THE GAS-COOLED NEUTRON TARGET +FLAG (1.) Data obtained with the gas-cooled neutron target MONITOR (1-H-1(N,EL)1-H-1,,SIG) -MONIT-REF (,UTLLEY,R,IAEA-227,1983) -ENDBIB 4 -NOCOMMON +MONIT-REF (,C.Utlley,R,IAEA-227,1983) +ERR-ANALYS (MONIT-ERR,0.7,0.9) MONITOR cross-section error +STATUS (TABLE) Table 4 of J,AE,65,(5),348,1988. +ENDBIB 6 +NOCOMMON 0 0 DATA 6 13 EN EN-RSL DATA ERR-T MONIT FLAG KEV KEV B PER-CENT B NO-DIM @@ -373,5 +410,5 @@ KEV KEV B PER-CENT B NO-DIM 785.11 30. 1.08 4.3 1. 785.12 30. 1.09 4.3 1. ENDDATA 15 -ENDSUBENT 24 +ENDSUBENT 26 ENDENTRY 11 diff --git a/exforall/409/40986.x4 b/exforall/409/40986.x4 index 96f7f2c01..7cdf1cef5 100644 --- a/exforall/409/40986.x4 +++ b/exforall/409/40986.x4 @@ -1,39 +1,53 @@ -ENTRY 40986 950403 20050926 0000 -SUBENT 40986001 950403 20050926 0000 -BIB 11 15 -TITLE NEUTRON RESONANCES OF THE RADIACTIVE (T1/2=241.6D) - GADOLINIUM-153 ISOTOPE -AUTHOR (V.P.VERTEBNYY,P.N.VORONA,A.I.KAL'CHENKO,V.G.KRIVENKO, - V.YU.CHERVYAKOV,L.E.CHERVONNAYA) -INSTITUTE (4CCPIJI) -REFERENCE (C,87KIEV,2,220,8709) - (J,AE,57,(4),260,8410) EXPERIMENTAL DETAILS -FACILITY (REAC) WWR-M -METHOD (TOF) FLIGHT BASE IS 69.47 M -DETECTOR (PROPC) BATTERY OF HE-3 COUNTERS -STATUS DATA ARE TAKEN FROM THE FIRST REFERENCE -MONITOR NO INFORMATION -ERR-ANALYS (DATA-ERR) ERRORS ARE NOT SPECIFIED -HISTORY (890911C) COMPILED AT THE CENTRE - CJD - (950403A) DATA VALUE IN SAN 004 CORRECTED -ENDBIB 15 +ENTRY 40986 20110714 20111003 20110930 4153 +SUBENT 40986001 20110714 20111003 20110930 4153 +BIB 12 25 +TITLE Neutron resonances of the radioactive (T1/2=241.6d) + gadolinium-153 isotope +AUTHOR (V.P.Vertebnyy,P.N.Vorona,A.I.Kal'chenko,V.G.Krivenko, + V.Yu.Chervyakov,L.E.Chervonnaya) +INSTITUTE (4UKRIJD) +REFERENCE (C,87KIEV,2,220,198709) Main reference. +REL-REF (M,40860001,V.P.Vertebnyy+,J,AE,57,(4),260,198410) + Experimental details of method. + (M,40860001,V.P.Vertebnyy+,J,SJA,57,(4),718,198410) + Engl. translation of J,AE . +FACILITY (REAC,4UKRIJD) WWR-M reactor. +METHOD (TOF) Flight base is 69.47 m + (TRN) Transmission. +DETECTOR (PROPC) Battery of He-3 counters +SAMPLE The sample of concentration 10 times higher than in + ENTRY 40860. +STATUS Data are taken from C,87KIEV,2,220,1987 +ERR-ANALYS (DATA-ERR) Errors are not specified +HISTORY (19890911C) Compiled at the centre - CJD + (19950403A) Data value in SAN 004 corrected + (20110714A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + BIB information was added. J,AE was moved in REL-REF. + Ref. J,SJA was added as REL-REF. + Subent 005 was added. +ENDBIB 25 COMMON 1 3 EN-RSL MICROSEC/M 5.5E-02 ENDCOMMON 3 -ENDSUBENT 22 -SUBENT 40986002 890911 20050926 0000 -BIB 1 3 -REACTION 1(64-GD-153(N,0),,EN) RESONANCE ENERGY - 2(64-GD-153(N,EL),,WID/RED,,G) - 3(64-GD-153(N,G),,WID) GAMMA-WIDTH -ENDBIB 3 -NOCOMMON +ENDSUBENT 32 +SUBENT 40986002 20110714 20111003 20110930 4153 +BIB 3 7 +REACTION 1(64-GD-153(N,0),,EN) Resonance energy + 2(64-GD-153(N,EL),,WID/RED,,G) gGn0 + 3(64-GD-153(N,G),,WID) Gamma-width +STATUS (TABLE) Table 1 of C,87KIEV,2,220,1987. +HISTORY (20110714A) M.M. DATA 3 were corrected 6. -> 65. meV + as given in Table 1 and text, page 221, of + C,87KIEV,2,220,1987 +ENDBIB 7 +NOCOMMON 0 0 DATA 6 10 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 3 EV EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV - 2.97E-02 2.5E-03 8.9E-02 8.E-03 6. 5. + 2.97E-02 2.5E-03 8.9E-02 8.E-03 65. 5. 6.65 0.015 9.45 14.56 0.05 @@ -44,31 +58,47 @@ EV EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV 54.6 0.3 60.8 0.4 ENDDATA 12 -ENDSUBENT 20 -SUBENT 40986003 890911 20050926 0000 -BIB 1 2 -REACTION 1(64-GD-152(N,0),,EN) RESONANCE ENERGY - 2(64-GD-152(N,G),,WID) GAMMA-WIDTH -ENDBIB 2 -NOCOMMON +ENDSUBENT 24 +SUBENT 40986003 20110714 20111003 20110930 4153 +BIB 2 3 +REACTION 1(64-GD-152(N,0),,EN) Resonance energy + 2(64-GD-152(N,G),,WID) Gamma-width +STATUS (TABLE) Text, page 223 of C,87KIEV,2,220,1987. +ENDBIB 3 +NOCOMMON 0 0 DATA 3 2 DATA 1DATA 2DATA-ERR 2 EV EV EV 8. 12.35 7.7E-02 1.3E-02 ENDDATA 4 -ENDSUBENT 11 -SUBENT 40986004 950403 20050926 0000 -BIB 3 3 +ENDSUBENT 12 +SUBENT 40986004 20110714 20111003 20110930 4153 +BIB 4 4 REACTION (64-GD-153(N,TOT),,SIG) DECAY-DATA (64-GD-153,241.6D) -HISTORY (950403A) DATA VALUE CORRECTED -ENDBIB 3 -NOCOMMON +STATUS (TABLE) Text, page 222 of C,87KIEV,2,220,1987. +HISTORY (19950403A) Data value corrected +ENDBIB 4 +NOCOMMON 0 0 DATA 3 1 EN DATA DATA-ERR EV B B 2.53E-02 2.3E+04 2.0E+03 ENDDATA 3 -ENDSUBENT 11 -ENDENTRY 4 +ENDSUBENT 12 +SUBENT 40986005 20110714 20111003 20110930 4153 +BIB 3 4 +REACTION (64-GD-153(N,0),,D) +STATUS (TABLE) Text, page 222 of C,87KIEV,2,220,1987. + (DEP,40986002) Res. parameters. +HISTORY (19950403A) Data value corrected +ENDBIB 4 +NOCOMMON 0 0 +DATA 3 1 +EN-RES-MAX DATA DATA-ERR +EV EV EV + 21. 3.0 0.6 +ENDDATA 3 +ENDSUBENT 12 +ENDENTRY 5 diff --git a/exforall/409/40987.x4 b/exforall/409/40987.x4 index 8a3c069e2..dbf3ee599 100644 --- a/exforall/409/40987.x4 +++ b/exforall/409/40987.x4 @@ -1,50 +1,83 @@ -ENTRY 40987 20020729 20030127 20050926 0000 -SUBENT 40987001 20020729 20030127 20050926 0000 -BIB 11 24 +ENTRY 40987 20110722 20111003 20110930 4153 +SUBENT 40987001 20110722 20111003 20110930 4153 +BIB 16 55 INSTITUTE (4RUSKUR) -REFERENCE (J,AE,65,(5),356,198811) DATA TABLE IS GIVEN - (C,87KIEV,2,242,198709) DATA TABLE IS GIVEN -AUTHOR (YU.V.ADAMCHUK,M.A.VOSKANYAN,G.V.MURADYAN, - V.A.STEPANOV) -TITLE U-236 AND U-238 RADIATION CAPTURE CROSS-SECTION - IN THE NEUTRON ENERGY RANGE 10 - 50 KEV -FACILITY (LINAC) LINEAR ELECTRON ACCELERATOR 'FAKEL' - TORCH -METHOD MULTIPLICITY SPECTROMETRY METHOD -DETECTOR (NAICR) 24-SECTION 4PI DETECTOR -MONITOR NO INFORMATION -ERR-ANALYS (ERR-2) MAX ERROR DUE TO THE BACKGROUND EXCLUSION - (ERR-3) MAX ERROR DUE TO THE TIME-OF-FLIGHT SCALE - SHIFT - (ERR-4) ERROR DUE TO THE NONCOMPLETE NEUTRON ABSORP- - TION AT THE SATURATED RESONANCE 6.67 EV - (ERR-5) ERROR DUE TO THE SAMPLE THICKNESS - DETERMINATION -STATUS DATA ARE TAKEN FROM THE REFERENCE -HISTORY (19890913C) COMPILED AT THE CENTRE - CJD - (19901017U) 'AV' ADDED IN SF8 IN SAN 002, 003 - (19940417A) NEW REFERENCE AND DATA IN SAN 004, 005 - ADDED ONE AUTHOR NAME CORRECTED - ADAMCHUK +REFERENCE (J,AE,65,(5),356,198811) Data table is given + (J,SJA,65,(5),930,1988) Engl.translation of J,AE,65 . + #doi:10.1007/BF01121254 + (C,87KIEV,2,242,198709) Data table is given +AUTHOR (Yu.V.Adamchuk,M.A.Voskanyan,G.V.Muradyan, + V.A.Stepanov) +REL-REF (M,,G.Muradyan+,J,NSE,90,(1),60,1985) Method details. +TITLE U-236 and U-238 radiative capture cross-sections + neutron energies from 10 eV to 50 keV +FACILITY (LINAC,4RUSKUR) Linear electron accelerator 'FAKEL' +METHOD Multiplicity spectrometry method + (TOF) Flight base 10.5 m. Resolution 4 ns/m. +DETECTOR (NAICR) 24-section 4PI detector of NaI(Tl) crystals. + Geometry efficiency about 95%,total volume about 160 l. + Protected by Li6H+paraffin of 6 g/cm**2; B-10 layer + 0.2 g/cm**2. + Registration efficiency of capture events is near 100%. + Threshold of discrimination about 1 MeV. +SAMPLE B-10 6.735E-4 atom/barn - to incident neutron spectrum + measurement. +INC-SPECT Neutron spectrum was calibrated by 6.67 eV resonance. +MONITOR 5-B-10(N,A) was used for incident spectrum. +ERR-ANALYS (ERR-2,0.1,2.) Error due to the background exclusion + (ERR-3,0.1,1.5) Error due to the time-of-flight scale + shift + (ERR-4) error due to the noncomplete neutron absorp- + tion at the saturated resonance 6.67 eV + (ERR-5) Error due to the sample thickness + determination + Error of energy dependence of B-10(n,alpha) - + about 2.E-5*EN, eV. + (ERR-T) Total error = square root of sum of all errors. +CORRECTION For self-absorption, multiple scattering. + For backgrounds. +ADD-RES Average weighted multiplicity spectra for s- and + p-resonances, calculated for 20 s-resonances and for + 18 p-resonances with average weighted errors: + k Momentum l =0 l=1 + 1 6.82+-0.02 6.90+-0.56 + 2 28.56+-0.03 27.90+-0.51 + 3 35.99+-0.03 35.34+-0.37 + 4 20.63+-0.03 20.78+-0.25 + 5 6.57+-0.02 7.17+-0.14 + 6 1.42+-0.01 1.71+-0.07 +STATUS (TABLE) Data are taken from the J,AE,65,(5),356,1988 +HISTORY (19890913C) Compiled at the centre - CJD + (19901017U) 'AV' added in SF8 in SAN 002, 003 + (19940417A) New reference and data in SAN 004, 005 + added.One author name corrected - Adamchuk (20020729U) Date corrected -ENDBIB 24 -COMMON 4 3 -ERR-2 ERR-3 ERR-4 ERR-5 -PER-CENT PER-CENT PER-CENT PER-CENT - 2. 1.5 0.3 0.5 + (20110722A) Upper -> lower case correction. + Reference of Engl.translation was added. + BIB information was added. + ERR-1 -> ERR-SYS. +ENDBIB 55 +COMMON 2 3 +ERR-4 ERR-5 +PER-CENT PER-CENT + 0.3 0.5 ENDCOMMON 3 -ENDSUBENT 31 -SUBENT 40987002 20020729 20030127 20050926 0000 -BIB 4 7 +ENDSUBENT 62 +SUBENT 40987002 20110722 20111003 20110930 4153 +BIB 5 9 REACTION (92-U-236(N,G)92-U-237,,SIG,,AV) -SAMPLE SAMPLE WEIGHT IS 2.62 GRAM, U-236 CONTENT 99.845%, - THICKNESS 9.443E-04 ATOMS/BARN -ERR-ANALYS (ERR-1) TOTAL SYSTEMATIC ERROR EQUAL TO SUM OF ERRORS - FROM ERR-2 TO ERR-5 -HISTORY (19901017U) 'AV' ADDED IN SF8 - (19940417U) ERR-ANALYS KEYWORD ADDED -ENDBIB 7 +SAMPLE Sample weight is 2.62 gram, enrichment 99.845%, + thickness 9.443E-04 atoms/barn +ERR-ANALYS (ERR-SYS) Total systematic error equal to sum of errors + from ERR-2 to ERR-5 +STATUS (TABLE) Table 2 of the J,AE,65,(5),356,1988 + (COREL,41354002) Measurement by different detector. +HISTORY (19901017U) 'AV' added in SF8 + (19940417U) ERR-ANALYS keyword added +ENDBIB 9 NOCOMMON 0 0 DATA 6 22 -EN-MIN EN-MAX DATA ERR-S ERR-1 ERR-T +EN-MIN EN-MAX DATA ERR-S ERR-SYS ERR-T KEV KEV B PER-CENT PER-CENT PER-CENT 0.1 0.2 14.8 0.3 1.3 0.7 0.2 0.3 7.89 0.4 1.3 0.7 @@ -69,20 +102,21 @@ KEV KEV B PER-CENT PER-CENT PER-CENT 30. 40. 0.523 0.8 4.4 2.2 40. 50. 0.476 1.0 5.2 2.6 ENDDATA 24 -ENDSUBENT 36 -SUBENT 40987003 20020729 20030127 20050926 0000 -BIB 4 7 +ENDSUBENT 38 +SUBENT 40987003 20110722 20111003 20110930 4153 +BIB 5 8 REACTION (92-U-238(N,G)92-U-239,,SIG,,AV) -SAMPLE SAMPLE WEIGHT IS 2.6 GRAM, U-238 COONTENT IS 99.999%, - THICKNESS 9.734E-04 ATOMS/BARN -ERR-ANALYS (ERR-1) TOTAL SYSTEMATIC ERROR EQUAL TO SUM OF ERRORS - FROM ERR-2 TO ERR-5 -HISTORY (19901017U) 'AV' ADDED IN SF8 - (19940417U) ERR-ANALYS KEYWORD ADDED -ENDBIB 7 +SAMPLE Sample weight is 2.60 gram, enrichment 99.999%, + thickness 9.734E-04 atoms/barn +ERR-ANALYS (ERR-SYS) Total systematic error equal to sum of errors + from ERR-2 to ERR-5 +STATUS (TABLE) Table 2 of the J,AE,65,(5),356,1988 +HISTORY (19901017U) 'AV' added IN SF8 + (19940417U) ERR-ANALYS keyword added +ENDBIB 8 NOCOMMON 0 0 DATA 6 22 -EN-MIN EN-MAX DATA ERR-S ERR-1 ERR-T +EN-MIN EN-MAX DATA ERR-S ERR-SYS ERR-T KEV KEV B PER-CENT PER-CENT PER-CENT 0.1 0.2 16.3 0.3 1.3 0.7 0.2 0.3 8.42 0.4 1.3 0.7 @@ -107,13 +141,16 @@ KEV KEV B PER-CENT PER-CENT PER-CENT 30. 40. 0.396 0.8 4.4 2.2 40. 50. 0.360 1.0 5.2 2.6 ENDDATA 24 -ENDSUBENT 36 -SUBENT 40987004 20020729 20030127 20050926 0000 -BIB 2 3 -REACTION (92-U-238(N,G)92-U-239,,SIG,,AV) AVERAGED OVER 1/E - SPECTRUM IN THE ENERGY GROUP INTERVALS -HISTORY (19940417C) + + COMPILED AT THE CENTRE + + -ENDBIB 3 +ENDSUBENT 37 +SUBENT 40987004 20110722 20111003 20110930 4153 +BIB 3 6 +REACTION (92-U-238(N,G)92-U-239,,SIG,,EPI) Averaged over 1/E + spectrum in the energy group intervals +STATUS (TABLE) Table 3 of the J,AE,65,(5),356,1988 +HISTORY (19940417C) + + Compiled at the centre + + + (20110722A) AV -> EPI according to the comment of + N.Otsuka (NDS IAEA). +ENDBIB 6 NOCOMMON 0 0 DATA 3 11 EN-MIN EN-MAX DATA @@ -130,13 +167,17 @@ KEV KEV B 10.0 21.5 0.573 21.5 46.5 0.414 ENDDATA 13 -ENDSUBENT 21 -SUBENT 40987005 20020729 20030127 20050926 0000 -BIB 2 3 -REACTION (92-U-236(N,G)92-U-237,,SIG,,AV) AVERAGED OVER 1/E - SPECTRUM IN THE ENERGY GROUP INTERVALS -HISTORY (19940417C) + + COMPILED AT THE CENTRE + + -ENDBIB 3 +ENDSUBENT 24 +SUBENT 40987005 20110722 20111003 20110930 4153 +BIB 3 7 +REACTION (92-U-236(N,G)92-U-237,,SIG,,EPI) Averaged over 1/E + spectrum in the energy group intervals +STATUS (TABLE) Table 3 of the J,AE,65,(5),356,1988 + (COREL,41354003) Measurement by different detector. +HISTORY (19940417C) + + Compiled at the centre + + + (20110722A) AV -> EPI according to the comment of + N.Otsuka (NDS IAEA). +ENDBIB 7 NOCOMMON 0 0 DATA 3 10 EN-MIN EN-MAX DATA @@ -152,5 +193,5 @@ KEV KEV B 10.0 21.5 0.716 21.5 46.5 0.548 ENDDATA 12 -ENDSUBENT 20 +ENDSUBENT 24 ENDENTRY 5 diff --git a/exforall/410/41044.x4 b/exforall/410/41044.x4 index 833ab1fde..e839550e5 100644 --- a/exforall/410/41044.x4 +++ b/exforall/410/41044.x4 @@ -1,41 +1,65 @@ -ENTRY 41044 910531 20050926 0000 -SUBENT 41044001 910531 20050926 0000 -BIB 14 19 -TITLE MEASUREMENTS OF THE ALPHA-VALUE FOR U-235 -AUTHOR (YU.V.ADAMCHUK,M.A.VOSKANYAN,G.GEORGIEV,A.L.KOVTUN, - G.V.MURADYAN,N.STANCHEVA,N.CHIKOV,N.YANEVA, - YU.G.SHCHEPKIN) -INSTITUTE (4CCPKUR,3BULBLA) -FACILITY (REAC),3BULBLA) -REFERENCE (J,AE,65,(6),434,8812) -MONITOR ABSOLUTE MEASUREMENT -METHOD (TOF) FLIGHT BASE IS 3 M +ENTRY 41044 20110722 20111003 20110930 4153 +SUBENT 41044001 20110722 20111003 20110930 4153 +BIB 16 39 +TITLE Measuring the U-235 ALPHA-values at a thermal point . +AUTHOR (Yu.V.Adamchuk,M.A.Voskanyan,G.Georgiev,A.L.Kovtun, + G.V.Muradyan,N.Stancheva,N.Chikov,N.Yaneva, + Yu.G.Shchepkin) +INSTITUTE (4RUSKUR,3BULBLA) +FACILITY (REAC,3BULBLA) +REFERENCE (J,AE,65,(6),434,198812) + (J,SJA,65,(6),1022,1988) Engl. translation of J,AE,65. + #doi:10.1007/BF01122477 +REL-REF (I,,Yu.Adamchuk+,J,NIM/A,236,105,1985) Details of + spectrometer. + (M,40581001,G.V.Muradyan+,R,IAE-3769,1983) + Details of method. + (M,40840001,Yu.V.Adamchuk+,J,AE,57,(4),251,1984) + Details of method. + (M,40840001,Yu.V.Adamchuk+,J,SJA,57,(4),705,1984) + Engl. translation of J,AE,57 . +INC-SOURCE (REAC) +INC-SPECT Thermal neutrons of reactor went through the multi-slot + collimator and then were made monochromatic by + two-disks mechanical selector. +METHOD (TOF) Flight base is 3 m (COINC) -ANALYSIS SPECTROMETRY OF MULTIPLICITY OF THE GAMMA-QUANTA -DETECTOR (NAICR) - (SOLST) SURFACE-BARRIER DETECTORS +ANALYSIS Spectrometry of multiplicity of the gamma-quanta +DETECTOR (NAICR) 12-sections 4PI-detector on the base of NaI + crystals - to detect gammas and neutrons. + (SIBAR) Surface-barrier detectors - to detect FF. PART-DET (G,N,FF) -SAMPLE U-235 ON AL FOIL, MASS 20 MILLIGRAM, THICKNESS - 2 MILLIGRAM/CM2, U-235 CONTENT 99.9 PC -STATUS DATA TAKEN FROM THE REFERENCE -ERR-ANALYS (ERR-1) SYSTEMATIC ERROR -HISTORY (910531C) + + COMPILED AT THE CENTRE - CJD + + -ENDBIB 19 +SAMPLE U-235 layers on both sides of Al foil (10microm), + U-235 mass 20 milligram, thickness 2 milligram/cm**2, + uranium enrichment > 99.9%. +STATUS Data taken from J,AE,65,(6),434,1988 +ERR-ANALYS (ERR-SYS) Systematic error + (ERR-S) Statistical error. +HISTORY (19910531C) + + Compiled at the centre - CJD + + + (20110721A) Upper -> lower case correction. + Dates were corrected for 4-digits year. + Reference of Engl.translation was added. + BIB information was added. +ENDBIB 39 COMMON 3 3 -EN ERR-S ERR-1 +EN ERR-S ERR-SYS EV PER-CENT PER-CENT 2.53E-02 1.3 1.6 ENDCOMMON 3 -ENDSUBENT 26 -SUBENT 41044002 910531 20050926 0000 -BIB 1 1 +ENDSUBENT 46 +SUBENT 41044002 20110722 20111003 20110930 4153 +BIB 2 5 REACTION (92-U-235(N,ABS),,ALF) -ENDBIB 1 -NOCOMMON +STATUS (TABLE) Text, page 434, of J,AE,65,(6),434,1988 + (COREL,30745002) In 30745 - previous measurement with + other (thicker) sample by the same method and at + the same setup. +ENDBIB 5 +NOCOMMON 0 0 DATA 2 1 DATA ERR-T NO-DIM NO-DIM 0.1690 0.0035 ENDDATA 3 -ENDSUBENT 9 +ENDSUBENT 13 ENDENTRY 2 diff --git a/exforall/411/41162.x4 b/exforall/411/41162.x4 index c80db8dca..543fb7088 100644 --- a/exforall/411/41162.x4 +++ b/exforall/411/41162.x4 @@ -1,39 +1,110 @@ -ENTRY 41162 941013 20050926 0000 -SUBENT 41162001 941013 20050926 0000 -BIB 12 17 -TITLE MEASUREMENTS AND ESTIMATES OF THE AVERAGE ENERGY - OF NEUTRONS FROM THE U-236(N,F) REACTION -AUTHOR (A.M.TRUFANOV,G.N.LOVCHIKOVA,G.N.SMIRENKIN, - A.V.POLYAKOV,V.A.VINOGRADOV) +ENTRY 41162 20110729 20111003 20110930 4153 +SUBENT 41162001 20110729 20111003 20110930 4153 +BIB 12 31 +TITLE Measurements and estimates of the average energy + of neutrons from the U-235(N,F) reaction +AUTHOR (A.M.Trufanov,G.N.Lovchikova,G.N.Smirenkin, + A.V.Polyakov,V.A.Vinogradov) INSTITUTE (4RUSFEI) -REFERENCE (J,YF,57,(4),606,9404) AVERAGE ENERGY IS GIVEN - (J,AE,76,(3),197,9403) PRELIMINARY RESULTS +REFERENCE (J,YF,57,(4),606,199404) Average energy is given + (J,PAN,57,(4),572,1994) Engl.translation of J,YF . + (J,AE,76,(3),197,199403) Preliminary results + (J,AE/T,76,(3),195,1994) Engl.translation of J,AE . + #doi:10.1007/BF02408191 METHOD (TOF) -FACILITY (VDG) NEUTRON CASCADE GENERATOR KG-2.5 AND ELECTROSTA - TIC GENERATOR EGP-10M -INC-SOURCE (P-T) +FACILITY (VDG,4RUSFEI) Neutron cascade generator KG-2.5 and + electrostatic generator EGP-10M +INC-SOURCE (P-T) Solid and gas targets. PART-DET (N,FF) -DETECTOR (SOLST) STILBENE CRYSTAL DETECTOR FOR NEUTRONS - (FISCH) FISSION CHAMBER FOR FF -ERR-ANALYS (ERR-T) TOTAL ERROR -STATUS DATA ARE TAKEN FROM THE REFERENCE -HISTORY (941013C) + + COMPILED AT THE CENTRE - CJD + + -ENDBIB 17 -NOCOMMON -ENDSUBENT 20 -SUBENT 41162002 941013 20050926 0000 -BIB 3 4 -REACTION (92-U-235(N,F),PR,AKE,N) -SAMPLE METALLIC U-235 LAYERS, TOTAL WEIGHT 0.9 GRAM, - THICKNESS 1 MILLIGRAM/CM2, U-235 CONTENT 99 PC -MONITOR NO INFORMATION -ENDBIB 4 -NOCOMMON -DATA 3 2 -EN DATA ERR-T -MEV MEV MEV - 0.5 1.98 0.03 - 5.0 2.12 0.03 +DETECTOR (SOLST) Stilbene crystal detector for neutrons + 63 mm diameter, 39 mm high, with FEU-30. + Efficiency was defined relative to Cf-252 prompt + neutron spectrum. + (FISCH) Fission chamber for FF + Registration efficiency 80 %. + Filled with Ar+CO2(10%) at 0.8atm pressure. +SAMPLE Metallic U-235 layers, total weight 0.9 gram, + thickness 1 milligram/cm**2, U-235 content 99 %. +ERR-ANALYS (ERR-T) Total Error +HISTORY (19941013C) + + Compiled at the centre - CJD + + + (20110729A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + BIB information was added. + Refs. J,AE/T, J,PAN were added. + Subents 003-005 were added. +ENDBIB 31 +NOCOMMON 0 0 +ENDSUBENT 34 +SUBENT 41162002 20110729 20111003 20110930 4153 +BIB 6 11 +REACTION (92-U-235(N,F)0-NN-1,PR,KE) +ANALYSIS Contribution of neutrons of energy < Emin=0.5 MeV was + taken into account by extrapolation. +CORRECTION For effect of energy and angular correlation "neutron + second-neutron first" -0.5 % - in AKE . +MISC-COL (MISC)Corresponding temperature T . +STATUS (TABLE) Table 1 of J,YF,57,(4),606,1994 + Table 2 of J,AE,76,(3),197 -for EN=5 MeV. + (SPSDD,41238003) Superseded by newer publication. +HISTORY (20110729A) N was deleted from SF7, 0-NN-1 was added in + SF4 according to the comment of N.Otsuka (NDS IAEA) . +ENDBIB 11 +NOCOMMON 0 0 +DATA 5 2 +EN DATA ERR-T MISC MISC-ERR +MEV MEV MEV MEV MEV + 0.5 1.98 0.03 1.32 0.02 + 5.0 2.12 0.03 1.41 0.02 ENDDATA 4 -ENDSUBENT 13 -ENDENTRY 2 +ENDSUBENT 20 +SUBENT 41162003 20110729 20111003 20110930 4153 +BIB 3 8 +REACTION (92-U-235(N,F),PR,NU/DE,,NPD) + Spectrum normalized to 1. . +SAMPLE Metallic U-235 layers, total weight 0.9 gram, + thickness 1 milligram/cm**2, U-235 content 99 %. +STATUS (UNOBT) Request of data was sent 03-08-2011 to + Anatoly Trufanov - trufanov@ippe.ru. + Fig.2 of J,YF,57,(4),606,1994 - for EN=0.5, 5.0 MeV. + Fig.1a of J,AE,76,(3),197,1994 -for EN=5 MeV. +ENDBIB 8 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 12 +SUBENT 41162004 20110729 20111003 20110930 4153 +BIB 3 9 +REACTION ((92-U-235(N,F),PR,NU/DE,,NPD)// + (98-CF-252(0,F),PR,NU/DE,,NPD)) + Ratio to standard Cf-252 SF spectrum +SAMPLE Metallic U-235 layers, total weight 0.9 gram, + thickness 1 milligram/cm**2, U-235 content 99 %. +STATUS (UNOBT) Request of data was sent 03-08-2011 to + Anatoly Trufanov - trufanov@ippe.ru. + Fig.3 of J,YF,57,(4),606,1994 - for EN=0.5, 5.0 MeV. + Fig.1b of J,AE,76,(3),197 -for EN=5 MeV. +ENDBIB 9 +COMMON 1 3 +EN +MEV + 5. +ENDCOMMON 3 +NODATA 0 0 +ENDSUBENT 17 +SUBENT 41162005 20110729 20111003 20110930 4153 +BIB 3 7 +REACTION (92-U-235(N,F),PR,NU/DE,,MXD) + Ratio to Maxwellian spectrum with T=1.407 MeV. +SAMPLE Metallic U-235 layers, total weight 0.9 gram, + thickness 1 milligram/cm**2, U-235 content 99 %. +STATUS (UNOBT) Request of data was sent 03-08-2011 to + Anatoly Trufanov - trufanov@ippe.ru. + Fig.1v of J,AE,76,(3),197 -for EN=5 MeV. +ENDBIB 7 +COMMON 2 3 +EN KT-NRM +MEV MEV + 5. 1.407 +ENDCOMMON 3 +NODATA 0 0 +ENDSUBENT 15 +ENDENTRY 5 diff --git a/exforall/411/41170.x4 b/exforall/411/41170.x4 index 2fb89b56c..1b0c694a5 100644 --- a/exforall/411/41170.x4 +++ b/exforall/411/41170.x4 @@ -1,34 +1,46 @@ -ENTRY 41170 20010311 20011019 20050926 0000 -SUBENT 41170001 20010311 20011019 20050926 0000 -BIB 13 18 -INSTITUTE (4UKRIJI) -REFERENCE (J,AE,77,(1),44,199407) DATA ARE GIVEN - (R,KIYAI-89-26,1989) EXPERIMENYAL DETAILS - (R,KIYAI-85-35,1985) EXPERIMENYAL DETAILS -AUTHOR (O.A.PURTOV, L.L.LITVINSKIY, A.V.MURZIN, G.M.NOVOSELOV) -TITLE TOTAL NEUTRON CROSS-SECTIONS AND WEIGHTED RESONANCE - PARAMETERS -FACILITY (REAC) REACTOR WWR-M -INC-SPECT FILTERED NEUTRON SPECTRUM -SAMPLE METALLIC CYLINDRICAL SAMPLES, CHEMICAL PURITY - IS 99.99 PC -METHOD TRANSMISSION METHOD -DETECTOR (PROPC) HE-3 AND H-FILLED PROPORTIONAL COUNTERS -MONITOR NO INFORMATION -ERR-ANALYS (DATA-ERR) ERRORS ARE NOT SPECIFIED -STATUS DATA ARE TAKEN FROM THE REFERENCE ONE -HISTORY (19950516C) + + COMPILED AT THE CENTRE - CJD + + +ENTRY 41170 20110728 20111003 20110930 4153 +SUBENT 41170001 20110728 20111003 20110930 4153 +BIB 13 29 +INSTITUTE (4UKRIJD) +REFERENCE (J,AE,77,(1),44,199407) Data are given + (J,AE/T,77,(1),536,1994) Engl.translation of J,AE,77. + #doi:10.1007/BF02408211 + (R,KIYAI-89-26,1989) Details of method + (R,KIYAI-85-35,1985)Details of setup. + First author L.L.Litvinskiy. +AUTHOR (O.A.Purtov, L.L.Litvinskiy, A.V.Murzin, G.M.Novoselov) +TITLE Total neutron cross-sections and average resonance + parameters of gold . +FACILITY (REAC,4UKRIJD) Reactor WWR-M +INC-SPECT Filtered neutron spectrum +SAMPLE Metallic cylindrical samples, chemical purity + is 99.99 % of different thickness. 10.05 mm diameter. +METHOD (TRN) Transmission method + (FNB) Filtered neutron beam +DETECTOR (PROPC) He-3 and H-filled proportional counters + SNM-52, SNM-38 +ANALYSIS Monte-Carlo method, least squares method, single level + R-matrix formalism were used. Doppler broadening was + taken into account according to REL-REF of + G.M.Novoselov+ . +REL-REF (M,,G.M.Novoselov+,R,KIYAI-89-25,1989) +STATUS Data are taken from J,AE,77,(1),44,1994 +HISTORY (19950516C) + + Compiled at the centre - CJD + + (20010311A) DATE is corrected -ENDBIB 18 + (20110727A) M.M. Upper -> lower case correction. + Ref. J,AE/T,77 was added. + BIB information was added. +ENDBIB 29 NOCOMMON 0 0 -ENDSUBENT 21 -SUBENT 41170002 20010311 20011019 20050926 0000 -BIB 2 4 -REACTION (79-AU-197(N,TOT),,SIG,,AV) AVERAGED OVER - ENERGY BAND WIDTH -FLAG (1.) DATA ARE OBTAINED ON NI-58 FILTER - THICKNESS IS 210 GRAM/CM2 -ENDBIB 4 +ENDSUBENT 32 +SUBENT 41170002 20110728 20111003 20110930 4153 +BIB 3 5 +REACTION (79-AU-197(N,TOT),,SIG,,AV) Averaged over + energy band width +FLAG (1.) Data are obtained on Ni-58 filter of + thickness 210 gram/cm**2 +STATUS (TABLE) Table 1 of J,AE,77,(1),44,1994. +ENDBIB 5 NOCOMMON 0 0 DATA 5 17 EN-MEAN EN-RSL-HW DATA DATA-ERR FLAG @@ -51,13 +63,14 @@ EV EV B B NO-DIM 3.43E+05 6.47 .45 1. 4.65E+05 6.96 .07 1. ENDDATA 19 -ENDSUBENT 28 -SUBENT 41170003 20010311 20011019 20050926 0000 -BIB 1 1 +ENDSUBENT 29 +SUBENT 41170003 20110728 20111003 20110930 4153 +BIB 2 2 REACTION (79-AU-197(N,EL),,STF) -ENDBIB 1 +STATUS (TABLE) Table 2 of J,AE,77,(1),44,1994. +ENDBIB 2 COMMON 2 3 -EN-MIN EN-MAX +EN-RES-MIN EN-RES-MAX EV EV 1.8E+03 4.16E+05 ENDCOMMON 3 @@ -67,27 +80,29 @@ NO-DIM NO-DIM NO-DIM 0. 2.11E-04 5.E-06 1. 3.4 E-05 2.E-05 ENDDATA 4 -ENDSUBENT 14 -SUBENT 41170004 20010311 20011019 20050926 0000 -BIB 1 1 +ENDSUBENT 15 +SUBENT 41170004 20110728 20111003 20110930 4153 +BIB 2 2 REACTION (79-AU-197(N,EL)79-AU-197,,RAD) -ENDBIB 1 +STATUS (TABLE) Table 2 of J,AE,77,(1),44,1994. +ENDBIB 2 NOCOMMON 0 0 DATA 4 1 EN-MIN EN-MAX DATA DATA-ERR EV EV FERMI FERMI 1.8E+03 4.16E+05 9.23 0.05 ENDDATA 3 -ENDSUBENT 9 -SUBENT 41170005 20010311 20011019 20050926 0000 -BIB 1 1 +ENDSUBENT 10 +SUBENT 41170005 20110728 20111003 20110930 4153 +BIB 2 2 REACTION (79-AU-197(N,G),,WID,,AV) -ENDBIB 1 +STATUS (TABLE) Table 2 of J,AE,77,(1),44,1994. +ENDBIB 2 NOCOMMON 0 0 DATA 4 1 -EN-MIN EN-MAX DATA DATA-ERR +EN-RES-MIN EN-RES-MAX DATA DATA-ERR EV EV EV EV 1.8E+03 4.16E+05 0.138 0.021 ENDDATA 3 -ENDSUBENT 9 +ENDSUBENT 10 ENDENTRY 5 diff --git a/exforall/411/41172.x4 b/exforall/411/41172.x4 index b61f9e272..ddce2792c 100644 --- a/exforall/411/41172.x4 +++ b/exforall/411/41172.x4 @@ -1,46 +1,105 @@ -ENTRY 41172 950726 20050926 0000 -SUBENT 41172001 950726 20050926 0000 -BIB 13 18 -TITLE N-ALPHA REACTIONS CROSS-SECTIONS ON SN-112, 114, 116 - AT THE NEUTRON ENERGY 14.6 MEV -AUTHOR (P.M.GOPYCH,M.N.DEMCHENKO,I.M.ZALYUBOVSKIY, - P.S.KIZIM) +ENTRY 41172 20110727 20111003 20110930 4153 +SUBENT 41172001 20110727 20111003 20110930 4153 +BIB 11 25 +TITLE Th cross-sections of (N,ALPHA) reactions on + Sn-112, 114, 116 at the neutron energy 14.6 MeV +AUTHOR (P.M.Gopych,M.N.Demchenko,I.M.Zalyubovskiy, + P.S.Kizim) INSTITUTE (4UKRKHU) -REFERENCE (J,AE,78,(5),329,9505) DATA ARE GIVEN -FACILITY (VDG) NEUTRON GENERATOR NG-150M +REFERENCE (J,AE,78,(5),329,199505) Data are given + (J,AE/T,78,(5),323,1995) Engl.translation of J,AE,78 . + #doi:10.1007/BF02419256 +REL-REF (R,,U.Reus+,J,AND,29,193,1983) Ref. for decay data. +FACILITY (VDG,4UKRKHU) Neutron generator NG-150M METHOD (ACTIV) -DETECTOR (GELI) -MONITOR (50-SN-112(N,2N)50-SN-111,,SIG) - ((50-SN-112(N,D)49-IN-111,,SIG)+ +DETECTOR (GELI) Ge(Li) of 50 cm** volume, energy resolution + about 3.5 keV for Co-60. Pb-Cd-Cu protection to + suppress background. + Spectrometer was calibrated by Co-57, Sn-113, Ce-139, + Am-241 and Sn-122 standard sources. +ERR-ANALYS (DATA-ERR) Error is not specified +SAMPLE Sn-114 content IS 7.1+-1.5%, Sn-112 Content is not + given. Enriched Sn-112 sample of about 2g mass. +HISTORY (19950726C) + + Compiled at the centre - CJD + + + (20110727A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + Ref. J,AE/T was added. + BIB information was added. + Subents 003-004 were added. +ENDBIB 25 +NOCOMMON 0 0 +ENDSUBENT 28 +SUBENT 41172002 20110727 20111003 20110930 4153 +BIB 3 6 +REACTION (50-SN-112(N,A)48-CD-109,,SIG,,,DERIV) +ANALYSIS C-s value was defined as average of Subents 003,004 + data determined relative different monitor c-s. +STATUS (TABLE) Text, page 329, of J,AE,78,(5),329,1995 + (DEP,41172003) See + (DEP,41172004) ANALYSIS. +ENDBIB 6 +NOCOMMON 0 0 +DATA 4 1 +EN EN-ERR DATA DATA-ERR +EV EV MB MB + 1.46E+07 2.E+05 45. 10. +ENDDATA 3 +ENDSUBENT 14 +SUBENT 41172003 20110727 20111003 20110930 4153 +BIB 6 19 +REACTION (50-SN-112(N,A)48-CD-109,,SIG) +DECAY-DATA (48-CD-109,461.9D,DG,88.0,0.0361) + (49-IN-111-G,2.83D,DG,171.3,0.903) + (49-IN-111-G,2.83D,DG,245.4,0.94) + (50-SN-111,35.3MIN,DG) + Decay data used to define Sn-114 admixture in sample: + (50-SN-113-G,115.1D,DG,391.7,0.642) + Also the line was detected: + (50-SN-113-G,115.1D,DG,255.0,0.0185) +MONITOR ((MONIT1)50-SN-112(N,2N)50-SN-111,,SIG) + ((MONIT2)(50-SN-112(N,D)49-IN-111,,SIG)+ (50-SN-112(N,N+P)49-IN-111,,SIG)) ASSUMED (ASSUM,50-SN-114(N,2N)50-SN-113,,SIG) -ERR-ANALYS (DATA-ERR) ERROR IS NOT SPECIFIED -SAMPLE SN-114 CONTENT IS 7.1+-1.5%, SN-112 CONTENT IS NOT - GIVEN -STATUS DATA ARE TAKEN FROM THE REFERENCE ONE -HISTORY (950726C) + + COMPILED AT THE CENTRE - CJD + + -ENDBIB 18 +ANALYSIS Gamma-lines 88.0, 171.3, 245.4 keV lines were used + to define c-s using linear combination of MONII1 and + MONIT2. + To define the amount of Sn-114 in sample - gamma-lines + 171.3, 345.4, 391.7 keV were used by ASSUM . +STATUS (TABLE) Text, page 329, of J,AE,78,(5),329,1995 +ENDBIB 19 COMMON 6 3 -MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR ASSUM ASSUM-ERR +ASSUM ASSUM-ERR MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR MB MB MB MB MB MB - 1300. 210. 180. 110. 1160. 130. + 1160. 130. 1300. 210. 180. 110. ENDCOMMON 3 -ENDSUBENT 25 -SUBENT 41172002 950726 20050926 0000 -BIB 2 7 +DATA 4 1 +EN EN-ERR DATA DATA-ERR +EV EV MB MB + 1.46E+07 2.E+05 44. 11. +ENDDATA 3 +ENDSUBENT 31 +SUBENT 41172004 20110727 20111003 20110930 4153 +BIB 5 10 REACTION (50-SN-112(N,A)48-CD-109,,SIG) DECAY-DATA (48-CD-109,461.9D,DG,88.0,0.0361) - (49-IN-111-G,2.83D,DG,171.3,0.903) - (49-IN-111-G,2.83D,DG,245.4,0.94) (50-SN-111,35.3MIN,DG) - (50-SN-113-G,115.1D,DG,255.0,0.0185) (50-SN-113-G,115.1D,DG,391.7,0.642) -ENDBIB 7 -NOCOMMON 0 0 + (50-SN-113-G,115.1D,DG,255.0,0.0185) +MONITOR (50-SN-114(N,2N)50-SN-113,,SIG) +ANALYSIS C-s value was defined by the Sn-114 admixture amount + in sample determined in Subent 003 relative Sn-114(N,2N + c-s using lines 88.0, 255.0, 391.7 keV. +STATUS (TABLE) Text, page 329, of J,AE,78,(5),329,1995 +ENDBIB 10 +COMMON 2 3 +MONIT MONIT-ERR +MB MB + 1160. 130. +ENDCOMMON 3 DATA 4 1 EN EN-ERR DATA DATA-ERR EV EV MB MB - 1.46E+07 2.E+05 45. 10. + 1.46E+07 2.E+05 52. 18. ENDDATA 3 -ENDSUBENT 15 -ENDENTRY 2 +ENDSUBENT 22 +ENDENTRY 4 diff --git a/exforall/411/41183.x4 b/exforall/411/41183.x4 index d85867859..a4d8daa59 100644 --- a/exforall/411/41183.x4 +++ b/exforall/411/41183.x4 @@ -1,37 +1,51 @@ -ENTRY 41183 960401 20050926 0000 -SUBENT 41183001 960401 20050926 0000 -BIB 13 22 -TITLE NEUTRON RADIATION CROSS-SECTIONS BY THE TH-232 - AND AU-197 NUCLEI IN THE ENERGY RANGE 0.37 - 1 MEV -AUTHOR (A.N.DAVLETSHIN,E.V.TEPLOV,A.O.TIPUNKOV, - S.V.TIKHONOV,V.A.TOLSTIKOV) +ENTRY 41183 20110721 20111003 20110930 4153 +SUBENT 41183001 20110721 20111003 20110930 4153 +BIB 14 32 +TITLE Neutron radiation cross-sections by the Th-232 + and Au-197 nuclei in the energy range 0.37 - 1 MeV +AUTHOR (A.N.Davletshin,E.V.Teplov,A.O.Tipunkov, + S.V.Tikhonov,V.A.Tolstikov) INSTITUTE (4RUSFEI) -REFERENCE (J,YK,1993,(1),13,9303) - (J,AE,65,(5),343,88) EXPERIMENTAL DETAILS +REFERENCE (J,YK,1993,(1),13,199303) +REL-REF (M,40968001,A.N.Davletshin+,J,AE,65,(5),343,1988) + Experimental details of method. + (M,40968001,A.N.Davletshin+,J,SJA,65,(5),913,1988) + Engl.translation of J,AE,65. METHOD (ACTIV) -FACILITY (VDG) KG-2,5 FEI ACCELERATOR -INC-SPECT ENERGY RESOLUTION REPRESENTS SPECTRUM DISPERSION - OF THE NEUTRONS IMPINGING DETECTORS -INC-SOURCE (P-T) +FACILITY (VDG,4RUSFEI) KG-2.5 FEI accelerator +INC-SPECT Energy resolution represents spectrum dispersion + of the neutrons impinging detectors +INC-SOURCE (P-T) ScT2 targets of 0.64-0.90 mg/cm**2 thickness. + Air cooled. DETECTOR (GELI) -CORRECTION CORRECTIONS WERE CALCULATED BY THE MONTE-CARLO - METHOD. CORRECTIONS ON NEUTRON BACKGROUND AT THE - DETECTOR POSITION LAYS IN THE INTERVAL 1.6-2.4 - PERCENT, IN THE GOLD SAMPLE - UP TO 0.9 PERCENTS, - IN THE THORIUM SAMPLE - 0.0 PERCENT. -STATUS DATA ARE TAKEN FROM THE REFERENCE -ERR-ANALYS (ERR-T) ERROR CONSISTS OF THE SUM OF EXPERIMENTAL AND - CALCULATION ERRORS -HISTORY (960401C) + + COMPILED AT THE CENTRE - CJD + + -ENDBIB 22 +CORRECTION Corrections were calculated by the Monte-Carlo + method. Corrections on neutron background at the + detector position lays in the interval 1.6-2.4 + percent, in the gold sample - up to 0.9 percents, + in the thorium sample - 0.0 percent. +STATUS Data are taken from the reference +ERR-ANALYS (ERR-T) Error consists of the sum of experimental and + calculation errors + (ERR-1,0.3,0.5) Statistical error of calculated by + Monte-Carlo code values. +HISTORY (19960401C) + + Compiled at the centre - CJD + + + (20110721A) Upper -> lower case correction. + Dates were corrected for 4-digits year. + Reference of Engl.translations was added. + BIB information was added. +ENDBIB 32 NOCOMMON 0 0 -ENDSUBENT 25 -SUBENT 41183002 960401 20050926 0000 -BIB 3 3 +ENDSUBENT 35 +SUBENT 41183002 20110721 20111003 20110930 4153 +BIB 5 7 REACTION (79-AU-197(N,G)79-AU-198,,SIG) MONITOR (92-U-235(N,F),,SIG) -SAMPLE METALLIC DISK, DIAMETER 2 CM, WEIGTH NEAR 1 GRAM -ENDBIB 3 +DECAY-DATA (79-AU-198,,DG,411.8) +SAMPLE Metallic disk, diameter 2 cm, weight near 1 gram +STATUS (TABLE) Table 1 of J,YK,1993,(1),13,1993 + (COREL,41190002) In 41190 - different INC-SOURCE: + TiT, water cooled. +ENDBIB 7 NOCOMMON 0 0 DATA 4 5 EN EN-RSL DATA ERR-T @@ -42,16 +56,19 @@ KEV KEV MB PER-CENT 800. 32. 87.5 1.6 1000. 31. 80.5 3. ENDDATA 7 -ENDSUBENT 15 -SUBENT 41183003 960401 20050926 0000 -BIB 3 6 +ENDSUBENT 19 +SUBENT 41183003 20110721 20111003 20110930 4153 +BIB 5 9 REACTION 1(90-TH-232(N,G)90-TH-233,,SIG) 2(90-TH-232(N,G)90-TH-233,,SIG) MONITOR 1(79-AU-197(N,G)79-AU-198,,SIG) 2(92-U-235(N,F),,SIG) -SAMPLE THORIUM OXIDE IN THE CYLINDRICAL STAINLESS-STEEL - CONTAINERS, DIAMETER 2 CM, WEIGHT NEAR 1 GRAM -ENDBIB 6 +SAMPLE Thorium oxide in the cylindrical stainless-steel + containers, diameter 2 cm, weight near 1 gram +DECAY-DATA (92-U-233,,DG,311.9) After double Beta- decay of Th-232 + (79-AU-198,,DG,411.8) +STATUS (TABLE) Table 2 of J,YK,1993,(1),13,1993 +ENDBIB 9 NOCOMMON 0 0 DATA 6 5 EN EN-RSL DATA 1ERR-T 1DATA 2ERR-T @@ -62,5 +79,5 @@ KEV KEV MB PER-CENT MB PER-CENT 800. 32. 140. 3.5 137. 4.5 1000. 31. 113. 4.5 112. 3. ENDDATA 7 -ENDSUBENT 18 +ENDSUBENT 21 ENDENTRY 3 diff --git a/exforall/411/41192.x4 b/exforall/411/41192.x4 index 7db7877c9..a2c9a1d63 100644 --- a/exforall/411/41192.x4 +++ b/exforall/411/41192.x4 @@ -1,60 +1,113 @@ -ENTRY 41192 960328 20050926 0000 -SUBENT 41192001 960328 20050926 0000 -BIB 9 13 -TITLE FACILITY FOR THE DELAYED NEUTRONS STUDY AND PRELIMINA - RESULTS OF THE BETA-EFF DETERMINATION FOR U-233 - RELATIVE TO U-235 -AUTHOR (S.B.BORZAKOV,E.DERMENJIEV,YU.S.ZAMYATNIN,V.M.NAZAROV, - S.S.PAVLOV,A.D.ROGOV,I.RUSKOV) +ENTRY 41192 20110719 20111003 20110930 4153 +SUBENT 41192001 20110719 20111003 20110930 4153 +BIB 13 41 +TITLE Apparatus for studying delayed neutrons and preliminary + results of the determination of beta-eff for U-233 with + respect to U-235 . +AUTHOR (S.B.Borzakov,E.Dermenjiev,Yu.S.Zamyatnin,V.M.Nazarov, + S.S.Pavlov,A.D.Rogov,I.Ruskov) INSTITUTE (4ZZZDUB) -REFERENCE (J,AE,79,(3),231,9509) DATA ARE GIVEN -FACILITY (REAC) FAST PULS REACTOR IBR-2 -DETECTOR (PROPC) BATTERY OF 12 PROP.COUNTERS PLACED IN - POLYETHILEN -MONITOR NO INFORMATION -ERR-ANALYS (DATA-ERR) ERRORS ARE NOT SPECIFIED -HISTORY (960328C) + + COMPILED AT THE CENTRE - CJD + + -ENDBIB 13 +REFERENCE (J,AE,79,(3),231,199509) Data are given + (J,AE/T,79,(3),637,1995) Engl.translation of J,AE,79 . +REL-REF (I,,E.Dermendjiev+,P,JINR-E3-6,1993) + Details of neutron detector and electronics. +FACILITY (REAC,4ZZZDUB) Fast pulse reactor IBR-2 + Setup "ISOMER". + (CHOPS) Slow chopper at 30 m distance from reactor. +METHOD (ACTIV) Cyclic activation: activation time 10-50 msec, + measurement time about 150 msec - each cycle. + (FISCT) +DETECTOR (PROPC) Battery of 12 prop.counters placed in + polyethylene. Covered by Cd and borated polyethylene. + Detector efficiency was calculated by MCNP code to be + 20% at 2 MeV and about 1.5 times less at 0.1 MeV. +INC-SOURCE (REAC) Mirror neutron guide. Slow chopper at 30 m + distance from reactor. +INC-SPECT Thermal neutron beam at sample position + 2.E+5 /sec/cm**2. +CORRECTION Background was measured by Cd filter, 12 for U-235, + 37 % for U-233. +ERR-ANALYS (DATA-ERR) Errors are not specified +HISTORY (19960328C) + + Compiled at the centre - CJD + + + (20110715A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + BIB information was added. + Ref. J,SJA was added. + In REACTION denominator F),PR,NU) -> F),,NU) + because BETA-ef= NU(delayed neutrons)/NU(total) - + according to information and formula on page 231 of + J,AE,79,(3),231,1995 . + DATA-ERR 1, DATA-ERR 2 in Subent 002 were corrected + 1.4E-3 -> 1.4E-4 as given in Table of + J,AE,79,(3),231,1995. + In Subent 004 DATA was corrected 2.7E-3 -> 2.9E-3 , + DATA-ERR 1.E-4 -> 2.E-4 as given in text. +ENDBIB 41 NOCOMMON 0 0 -ENDSUBENT 16 -SUBENT 41192002 960328 20050926 0000 -BIB 2 4 -REACTION 1((92-U-235(N,F),DL,NU)/(92-U-235(N,F),PR,NU)) - 2((92-U-235(N,F),DL,NU)/(92-U-235(N,F),PR,NU)) -SAMPLE 1 METALLIC DISK 50-80 MM IN DIAMETER, MASS 7 GRAM - 2 METALLIC DISK 50-80 MM IN DIAMETER, MASS 0.3 GRAM -ENDBIB 4 -NOCOMMON 0 0 -DATA 5 1 -EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 -EV NO-DIM NO-DIM NO-DIM NO-DIM - 2.5E-02 6.50E-3 1.4E-3 6.47E-03 1.4E-03 -ENDDATA 3 -ENDSUBENT 12 -SUBENT 41192003 960328 20050926 0000 -BIB 2 3 -REACTION ((92-U-233(N,F),DL,NU)/(92-U-235(N,F),PR,NU)) -SAMPLE METALLIC DISK 50-80 MM IN DIAMETER, MASS 7 GRAM - U-235 ADMISSION LESS THEN 0.2 PC -ENDBIB 3 +ENDSUBENT 44 +SUBENT 41192002 20110719 20111003 20110930 4153 +BIB 5 8 +REACTION ((92-U-235(N,F),DL,NU)/(92-U-235(N,F),,NU)) +SAMPLE 1 Metallic disk 50-80 mm in diameter, mass 7 gram + 2 Metallic disk 50-80 mm in diameter, mass 0.3 gram +ANALYSIS Ratio of registration efficiencies of delayed to + prompt neutron = 1.42+-0.02 was used. +FLAG (1.) Measured by sample 1. + (2.) Measured by sample 2. +STATUS (TABLE) Table of J,AE,79,(3),231,1995. +ENDBIB 8 +COMMON 1 3 +EN +EV + 2.5E-02 +ENDCOMMON 3 +DATA 3 2 +DATA DATA-ERR FLAG +NO-DIM NO-DIM NO-DIM + 6.50E-3 1.4E-4 1. + 6.47E-3 1.4E-4 2. +ENDDATA 4 +ENDSUBENT 21 +SUBENT 41192003 20110719 20111003 20110930 4153 +BIB 4 6 +REACTION ((92-U-233(N,F),DL,NU)/(92-U-233(N,F),,NU)) +SAMPLE Metallic disk 50-80 mm in diameter, mass 7 gram, + U-235 admixture less then 0.2 %. +ANALYSIS Ratio of registration efficiencies of delayed to + prompt neutron = 1.42+-0.02 was used. +STATUS (TABLE) Table of J,AE,79,(3),231,1995. +ENDBIB 6 NOCOMMON 0 0 DATA 3 1 EN DATA DATA-ERR EV NO-DIM NO-DIM 2.5E-02 2.77E-3 7. E-5 ENDDATA 3 -ENDSUBENT 11 -SUBENT 41192004 960328 20050926 0000 -BIB 2 3 -REACTION ((92-U-233(N,F),DL,NU)/(92-U-233(N,F),PR,NU)) -STATUS (DEP,41192002) - (DEP,41192003) -ENDBIB 3 -NOCOMMON 0 0 +ENDSUBENT 14 +SUBENT 41192004 20110719 20111003 20110930 4153 +BIB 5 12 +REACTION ((92-U-233(N,F),DL,NU)/(92-U-233(N,F),,NU)) +ASSUMED (ASSUM,(92-U-235(N,F),DL,NU)/(92-U-235(N,F),,NU)) + From REL-REF of J.Blachot+. +REL-REF (R,,J.Blachot+,R,NEACRP-L-323,1990) + (A,,E.Dermenjiev+,P,JINR-E3-7,1993) + Agree with value 0.0027+-0.0001 of E.Dermenjiev+. +ANALYSIS Using ASSUM value of BETA-ef from REL-REF, the ratio + of registration efficiencies of delayed to prompt + neutron was determined to be EPS-DN/EPS-PN=1.36 +-0.06, + what is in reasonable agreement with calculated. + BETA-ef was determined using this exp. ratio 1.36+-0.6. +STATUS (TABLE) Text, page 232 of J,AE,79,(3),231,1995. +ENDBIB 12 +COMMON 2 3 +ASSUM ASSUM-ERR +NO-DIM NO-DIM + 0.0068 0.0002 +ENDCOMMON 3 DATA 3 1 EN DATA DATA-ERR EV NO-DIM NO-DIM - 2.5E-02 2.7 E-3 1. E-4 + 2.5E-02 2.9 E-3 2. E-4 ENDDATA 3 -ENDSUBENT 11 +ENDSUBENT 24 ENDENTRY 4 diff --git a/exforall/411/41194.x4 b/exforall/411/41194.x4 index 2cb626257..9716c7963 100644 --- a/exforall/411/41194.x4 +++ b/exforall/411/41194.x4 @@ -1,43 +1,47 @@ -ENTRY 41194 19990820 19991117 20050926 0000 -SUBENT 41194001 19990820 19991117 20050926 0000 -BIB 14 23 -TITLE SM-149 NEUTRON RESONANCE PARAMETERS DETERMINATION - BY THE METHOD OF THE GAMMA-QUANTA MULTIPLICITY -AUTHOR (G.P.GEORGIEV,YU.V.GRIGOR'EV,YU.S.ZAMYATNIN, - G.V.MURADYAN,L.B.PIKEL'NER,KH.FAYKOV-STANCHIK, - N.B.YANEVA) -INSTITUTE (4ZZZDUB) GEORGIEV, ZAMYATNIN, PIKEL'NER, - FAYKOV-STANCHIK - (4RUSKUR) MURADYAN - (4RUSFEI) GRIGOR'EV - (3BULBLA) YANEVA +ENTRY 41194 20110816 20111003 20110930 4153 +SUBENT 41194001 20110816 20111003 20110930 4153 +BIB 14 26 +TITLE Sm-149 neutron resonance parameters determination + by the method of the gamma-quanta multiplicity +AUTHOR (G.P.Georgiev,Yu.V.Grigor'ev,Yu.S.Zamyatnin, + G.V.Muradyan,L.B.Pikel'ver,Kh.Faykov-Stanchik, + N.B.Yaneva) +INSTITUTE (4ZZZDUB) Georgiev, Zamyatnin, Pikel'Ner, + Faykov-Stanchik + (4RUSKUR) Muradyan + (4RUSFEI) Grigor'ev + (3BULBLA) Yaneva REFERENCE (R,JINR-P3-92-346,199209) -FACILITY (REAC,4ZZZDUB) FAST PULSE REACTOR IBR-30 +FACILITY (REAC,4ZZZDUB) Fast pulse reactor IBR-30 INC-SOURCE (REAC) -METHOD (TOF) FLIGHT BASE IS 500 M -DETECTOR (NAICR) BATTERY OF 16 SCINTILLATION DETECTORS +METHOD (TOF) Flight base is 500 m +DETECTOR (NAICR) Battery of 16 scintillation detectors ANALYSIS (AREA) MONITOR (5-B-10(N,G)5-B-11,,SIG,G) -SAMPLE SAMARIUM OXIDE, SM-149 CONTENT IS 94.6 PC, - THICKNES ON SM-149 IS 2.47E+20 ATOMS/CM2 -ERR-ANALYS (DATA-ERR) ERRORS ARE NOT SPECIFIED -STATUS .DATA ARE TAKEN FROM THE REFERENCE -HISTORY (19960701C) + + COMPILED AT THE CENTRE - CJD + + - (19990820U) . . DATES CORRECTED -ENDBIB 23 +SAMPLE Samarium oxide, Sm-149 content is 94.6 %, + thickness on Sm-149 is 2.47E+20 atoms/cm2 +ERR-ANALYS (DATA-ERR) Errors are not specified +STATUS (TABLE) Data from R,JINR-P3-92-346,199209 +HISTORY (19960701C) + + Compiled at the centre - CJD + + + (19990820U) . . Dates corrected + (20110816A) M.M. Subents were superseded by newer + publication. + Upper -> lower case correction. +ENDBIB 26 COMMON 1 3 EN-RSL NSEC/M 8. ENDCOMMON 3 -ENDSUBENT 30 -SUBENT 41194002 19990820 19991117 20050926 0000 -BIB 1 4 -REACTION 1(62-SM-149(N,0),,EN) RESONANCE ENERGY - 2(62-SM-149(N,EL),,WID) RESONANCE ELASTIC WIDTH - 3(62-SM-149(N,G),,WID) RESONANCE GAMMA WIDTH - 4(62-SM-149(N,0),,J) RESONANCE SPIN VALUE -ENDBIB 4 +ENDSUBENT 33 +SUBENT 41194002 20110816 20111003 20110930 4153 +BIB 2 5 +REACTION 1(62-SM-149(N,0),,EN) Resonance energy + 2(62-SM-149(N,EL),,WID) Resonance elastic width + 3(62-SM-149(N,G),,WID) Resonance gamma width + 4(62-SM-149(N,0),,J) Resonance spin value +STATUS (SPSDD,41345002) Superseded by newer publication. +ENDBIB 5 NOCOMMON 0 0 DATA 6 91 DATA 1DATA 2DATA-ERR 2DATA 3DATA-ERR 3DATA 4 @@ -134,17 +138,19 @@ EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV NO-DIM 268.9 4. 272.8 4. ENDDATA 93 -ENDSUBENT 102 -SUBENT 41194003 960701 19991117 20050926 0000 -BIB 1 2 -REACTION (62-SM-149(N,G),,WID,,AV) AVERAGED OVER 51 RESONANCES - GAMMA-WIDTH -ENDBIB 2 +ENDSUBENT 103 +SUBENT 41194003 20110816 20111003 20110930 4153 +BIB 2 4 +REACTION (62-SM-149(N,G),,WID,,AV) Averaged over 51 resonances + gamma-width +STATUS (SPSDD,41345003) Superseded as duplication. + (DEP,41194002) Averaged over 51 resonances . +ENDBIB 4 NOCOMMON 0 0 DATA 4 1 EN-MIN EN-MAX DATA DATA-ERR EV EV MILLI-EV MILLI-EV 25. 263. 75. 3. ENDDATA 3 -ENDSUBENT 10 +ENDSUBENT 12 ENDENTRY 3 diff --git a/exforall/411/41197.x4 b/exforall/411/41197.x4 index 748aed00f..feaba83f9 100644 --- a/exforall/411/41197.x4 +++ b/exforall/411/41197.x4 @@ -1,55 +1,63 @@ -ENTRY 41197 20010504 20050616 20050926 0000 -SUBENT 41197001 20010504 20050616 20050926 0000 -BIB 10 18 +ENTRY 41197 20110714 20111003 20110930 4153 +SUBENT 41197001 20110714 20111003 20110930 4153 +BIB 10 25 TITLE Investigation of Ba-134 Gamma-Radiation in the (N,N'GAMMA) Reaction -AUTHOR (A.M.DEMIDOV,I.V.MIKHAYLOV) +AUTHOR (A.M.Demidov,I.V.Mikhaylov) INSTITUTE (4RUSKUR) -REFERENCE (J,YF,58,(12),2115,199512) Data Table is Given - (J,AE,57,270,1984) Experimental Details -FACILITY (REAC) Reactor Ir-8 -DETECTOR (HPGE) Resolution is 1.9 - 2.1 KeV at 1.3 MeV - Gamma Energy, Efficiency is 10 Pc -INC-SPECT Fast Neutron Beam of the Thermal Reactor -SAMPLE Ba-C-O3 Sample, Mass 14.5 Gram, Size 4.3*4.1 Cm, - Ba-134 Content is 83 Pc, Ba-135 Content is 7.6 Pc, - Ba-136 Content is 1.6 Pc, Ba-137 Content is 1.4 Pc, - Ba-138 Content is 6.3 Pc -STATUS Data are Taken from the Reference +REFERENCE (J,YF,58,(12),2115,199512) Data tables are given + (J,PAN,58,(12),2001,1995) Engl.translation of J,YF . +REL-REF (M,41574001,L.I.Govor+,J,AE,57,(4),270,1984)Exp.details + (M,41574001,L.I.Govor+,J,SJA,57,(4),732,1984) + Engl.translation of J,AE . +FACILITY (REAC) Reactor IR-8 +DETECTOR (HPGE) Resolution is 1.9 - 2.1 keV at 1.3 MeV + gamma energy, efficiency is 10 %. +INC-SPECT Fast neutron beam of the thermal reactor +SAMPLE Ba-C-O3 sample, mass 14.5 gram, size 4.3*4.1 cm, + Ba-134 content is 83 % , Ba-135 content is 7.6 % , + Ba-136 content is 1.6 % , Ba-137 content is 1.4 % , + Ba-138 content is 6.3 % HISTORY (19960704C) + + Compiled at the Centre - CJD + + (20010313A) Date is Corrected (20010504A) Corrected at CJD -ENDBIB 18 + (20110714A) M.M. References of Engl.translations added. + J,AE was moved in REL-REF. + E-ERR -> E-NM-ERR . + Subents 004-005 were added. + In Subents 002,003: E-LVL-INI -> LVL-INI . +ENDBIB 25 COMMON 1 3 EN-DUMMY EV 1.E+06 ENDCOMMON 3 -ENDSUBENT 25 -SUBENT 41197002 20010504 20050616 20050926 0000 -BIB 6 14 +ENDSUBENT 32 +SUBENT 41197002 20110714 20111003 20110930 4153 +BIB 7 15 REACTION ((56-BA-134(N,INL)56-BA-134,,SPC,,FIS)// (56-BA-134(N,INL)56-BA-134,,SPC,,FIS)) Relative to 604.72-KeV Gamma-Line Taken For 100 Units EN-SEC (E-DN,G) (E-NM,G) - (E-LVL-INI,56-BA-134) -COMMENT .Gamma Rays Energy is Taken at the Angle 90 Degree - Relative to the Incident Neutron Beam -ERR-ANALYS (DATA-ERR) Errors are not Specified - (E-ERR) Error of the Nominator Gamma Energy -HISTORY (20010313U) Reaction Code Modified According to NNDC - Comment. Data Units Changed to 'No-Dim' - (20010504A) Data Values Diminished in 100 Times -FLAG (1.) Some Uncertainty in Initial Level is Present -ENDBIB 14 + (LVL-INI,56-BA-134) +COMMENT .Gamma rays energy is taken at the angle 90 degree + relative to the incident neutron beam +ERR-ANALYS (DATA-ERR) Errors are not specified + (E-NM-ERR) Error of the nominator gamma energy +STATUS (TABLE) Table 1 of J,YF,58,(12),2115,1995 +HISTORY (20010313U) Reaction Code modified according to NNDC + comment. Data units changed to 'NO-DIM' + (20010504A) Data values diminished in 100 times +FLAG (1.) Some uncertainty in initial level is present +ENDBIB 15 COMMON 1 3 E-DN KEV 604.72 ENDCOMMON 3 DATA 6 224 -E-NM E-ERR E-LVL-INI DATA DATA-ERR FLAG +E-NM E-NM-ERR LVL-INI DATA DATA-ERR FLAG KEV KEV KEV NO-DIM NO-DIM NO-DIM 132.4 0.4 2377. 0.026-2 0.008-2 165.7 0.8 2377. 0.025-2 0.006-2 @@ -276,15 +284,16 @@ KEV KEV KEV NO-DIM NO-DIM NO-DIM 3853.7 0.4 3854. 0.09-2 0.007-2 3875.5 1.2 0.014-2 0.006-2 ENDDATA 226 -ENDSUBENT 249 -SUBENT 41197003 960712 20050616 20050926 0000 -BIB 2 2 +ENDSUBENT 250 +SUBENT 41197003 20110714 20111003 20110930 4153 +BIB 3 3 REACTION (56-BA-134(N,INL)56-BA-134,PAR,DA,G,LEG/RS) -ERR-ANALYS (ERR-S) STATISTICAL ERROR AT 0.68 RELIABILITY LEVEL -ENDBIB 2 +ERR-ANALYS (ERR-S) Statistical error at 0.68 confidence level +STATUS (TABLE) Table 2 of J,YF,58,(12),2115,1995 +ENDBIB 3 NOCOMMON 0 0 DATA 5 174 -NUMBER E E-LVL-INI DATA ERR-S +NUMBER E LVL-INI DATA ERR-S NO-DIM KEV KEV NO-DIM NO-DIM 2. 194.66 2164.63 0.19 0.06 2. 309.88 2279.87 0.18 0.02 @@ -461,5 +470,90 @@ NO-DIM KEV KEV NO-DIM NO-DIM 4. 3684.1 3684.1 -0.07 0.15 4. 3853.7 3853.7 -0.08 0.11 ENDDATA 176 -ENDSUBENT 183 -ENDENTRY 3 +ENDSUBENT 184 +SUBENT 41197004 20110714 20111003 20110930 4153 +BIB 3 5 +REACTION (56-BA-134(N,INL)56-BA-134,PAR,DA,G,LEG/RS) + Legendre coefficients for gamma-lines, not placed in + level scheme. +ERR-ANALYS (DATA-ERR) Not specified. +STATUS (TABLE) Table 4 of J,YF,58,(12),2115,1995 +ENDBIB 5 +NOCOMMON 0 0 +DATA 4 26 +E NUMBER DATA DATA-ERR +KEV NO-DIM NO-DIM NO-DIM + 682.93 2. 0.37 0.04 + 682.93 4. 0.05 0.06 + 767.17 2. 0.74 0.08 + 767.17 4. 0.17 0.10 +1384.29 2. -0.03 0.11 +1384.29 4. -0.27 0.16 +1387.97 2. 0.20 0.08 +1387.97 4. -0.07 0.11 +1394.97 2. -0.03 0.04 +1394.97 4. -0.08 0.06 +1427.2 2. 0.45 0.10 +1427.2 4. 0.30 0.14 +1924.69 2. -0.02 0.06 +1924.69 4. 0.00 0.08 +2097.5 2. 0.30 0.14 +2097.5 4. 0.11 0.18 +2129.0 2. 0.22 0.12 +2129.0 4. 0.25 0.17 +2345.6 2. 0.06 0.05 +2345.6 4. -0.06 0.07 +2707.1 2. -0.11 0.09 +2707.1 4. -0.06 0.13 +3029.0 2. 0.31 0.18 +3029.0 4. -0.35 0.26 +3560.6 2. 0.17 0.10 +3560.6 4. 0.31 0.12 +ENDDATA 28 +ENDSUBENT 38 +SUBENT 41197005 20110714 20111003 20110930 4153 +BIB 4 8 +REACTION (56-BA-134(N,INL)56-BA-134,PAR,POL,G,MSC) + Gamma-ray linear polarization. +ANALYSIS Linear polarization P was determined by N = ratio of + counts measured at 90 degrees to 0 degrees by + polarimeter and R = sensitivity of polarimeter, + using relation P=(1-N*R)/(N-R). +ERR-ANALYS (DATA-ERR) Not specified. +STATUS (TABLE) Table 3 of J,YF,58,(12),2115,1995 +ENDBIB 8 +NOCOMMON 0 0 +DATA 4 28 +E DATA +DATA-ERR -DATA-ERR +KEV NO-DIM NO-DIM NO-DIM + 475.38 1.30 0.25 0.12 + 563.25 0.78 0.12 0.12 + 569.35 3.6 3.2 0.7 + 604.72 1.9 0.6 0.2 + 642.01 1.8 2.7 0.8 + 691.43 1.1 0.4 0.3 + 717.64 3.4 3.3 0.7 + 764.04 2.4 2.2 0.7 + 795.86 2.5 0.6 0.3 + 810.86 4. 6. 1. + 826.28 2.1 2.1 0.9 + 884.72 2.7 2.5 1.0 + 899.42 2.7 1.7 0.8 + 920.33 3. 6. 1. + 950.26 2.5 2.5 1.0 + 996.69 3.0 2.8 0.9 +1018.54 1.6 1.2 0.6 +1038.57 0.34 0.7 0.10 +1155.89 1.0 0.5 0.4 +1167.94 2.1 0.9 0.3 +1403.18 1.1 1.6 0.7 +1407.18 3. 15. 2. +1424.54 2.1 6. 3. +1483.52 1.8 0.4 0.3 +1649.95 2.2 0.6 0.4 +1675.08 0.7 0.4 0.4 +1730.07 2.0 1.8 1.0 +1766.19 3. 5. 2. +ENDDATA 30 +ENDSUBENT 43 +ENDENTRY 5 diff --git a/exforall/412/41236.x4 b/exforall/412/41236.x4 index 1d31c4d16..0ce988e4d 100644 --- a/exforall/412/41236.x4 +++ b/exforall/412/41236.x4 @@ -1,47 +1,33 @@ -ENTRY 41236 970227 20050926 0000 -SUBENT 41236001 970227 20050926 0000 -BIB 10 16 -TITLE CROSS SECTION OF (N,ALPHA) REACTION ON SN-112 - ON 14-MEV NEUTRONS -AUTHOR (P.M.GOPYCH,M.N.DEMCHENKO,I.I.ZALYUBOVSKIY,P.S.KIZIM) +ENTRY 41236 20110816 20111003 20110930 4153 +SUBENT 41236001 20110816 20111003 20110930 4153 +BIB 9 13 +TITLE Cross section of (N,ALPHA) reaction on Sn-112 + on 14-MeV neutrons +AUTHOR (P.M.Gopych,M.N.Demchenko,I.I.Zalyubovskiy,P.S.Kizim) INSTITUTE (4UKRKHU) -REFERENCE (C,95PETRBG,,250,9506) MAIN REFERENCE, DATA IS GIVEN - (C,95PETRBG,,491,9506) SUMMARY OF MAIN REFERENCE -FACILITY (VDG) NEUTRON GENERATOR NG-150M +REFERENCE (C,95PETRBG,,250,199506) Main reference, data is given + (C,95PETRBG,,491,199506) Summary of main reference +FACILITY (VDG) Neutron generator NG-150M DETECTOR (GELI) METHOD (ACTIV) -MONITOR (50-SN-112(N,2N)50-SN-111,,SIG) - ((50-SN-112(N,D)49-IN-111,,SIG)+ - (50-SN-112(N,N+P)49-IN-111,SEQ,SIG)+ - (50-SN-112(N,P+N)49-IN-111,SEQ,SIG)) - (50-SN-114(N,2N)50-SN-113,,SIG) -STATUS DATA ARE TAKEN FROM THE MAIN REFERENCE -HISTORY (970227C) + + COMPILED AT THE CENTRE - CJD + + -ENDBIB 16 -COMMON 3 3 -EN EN-ERR E-NRM -EV EV EV - 1.46+07 2.0+05 8.80+05 +STATUS Data are taken from C,95PETRBG,,250,1995 +HISTORY (19970227C) + + Compiled at the centre - CJD + + + (20110816A) M.M. Subent 002 was deleted as duplication + of 41172.002. +ENDBIB 13 +COMMON 2 3 +EN EN-ERR +EV EV + 1.46+07 2.0+05 ENDCOMMON 3 -ENDSUBENT 23 -SUBENT 41236002 970227 20050926 0000 -BIB 2 6 +ENDSUBENT 20 +SUBENT 41236002 20110716 20111003 20110930 4153 +BIB 3 3 REACTION (50-SN-112(N,A)48-CD-109,,SIG) -DECAY-DATA (50-SN-111,35.3MIN) - (49-IN-111-G,2.83D,DG,171.3,0.902) - (49-IN-111-G,2.83D,DG,245.4,0.940) - (50-SN-113-G,115.1D,DG,255.0,0.0185) - (50-SN-113-G,115.1D,DG,391.7,0.642) -ENDBIB 6 -COMMON 6 3 -MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR MONIT3 MONIT3-ERR -MB MB MB MB MB MB - 1300. 210. 180. 110. 1160. 130. -ENDCOMMON 3 -DATA 2 1 -DATA DATA-ERR -MB MB - 45. 10. -ENDDATA 3 -ENDSUBENT 18 +STATUS (SPSDD,41172002) Superseded as duplication. +HISTORY (20110816D) DATA were deleted as duplication of 41172. +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 ENDENTRY 2 diff --git a/exforall/412/41272.x4 b/exforall/412/41272.x4 index f3403ed52..d82386aaf 100644 --- a/exforall/412/41272.x4 +++ b/exforall/412/41272.x4 @@ -1,36 +1,105 @@ -ENTRY 41272 970807 20050926 0000 -SUBENT 41272001 970807 20050926 0000 -BIB 9 15 +ENTRY 41272 20110519 20111003 20110930 4153 +SUBENT 41272001 20110519 20111003 20110930 4153 +BIB 7 16 INSTITUTE (4RUSLEB) -REFERENCE (J,ZET,33,(1),9,5707) - (J,JET,6,6,5801) TRANSLATION -AUTHOR (A.A.BERGMAN,A.I.ISAKOV,YU.P.POPOV,F.L.SHAPIRO) -TITLE MEASUREMENTS WITH A SLOWING-DOWN-TIME NEUTRON SPECTRO- - METER EMPLOYING LEAD. EXCITED LEVEL OF THE HE-4 - NUCLEUS -FACILITY SLOWING-DOWN-TIME NEUTRON SPECTROMETER -METHOD (TOF) TIME OF FLIGHT PATH LENGTH CONSTANT TO WITHIN - 3-5 PER-CENT. BURST, CHANNEL WIDTHS ARE 0.5 MICRO-SEC - EACH. -DETECTOR (SCIN) STILBENE CRYSTAL SCINTILLATION COUNTER -ANALYSIS DATA DEDUCED FROM TOTAL CROSS SECTION OF B-10 IN THE - SAME ENERGY INTERVAL -HISTORY (970807T) + + COMPILED AT THE CENTER - CJD + + -ENDBIB 15 +REFERENCE (J,ZET,33,(1),9,195707) + (J,JET,6,6,195801) Engl. Translation + (C,55GENEVA,4,166,1955) Paper P/642. + Details of Pb slowing-down neutron spectrometer. +AUTHOR (A.A.Bergman,A.I.Isakov,Yu.P.Popov,F.L.Shapiro) +TITLE Measurements with a slowing-down-time neutron spectro- + meter employing lead. Excited level of the He-4 + nucleus. +METHOD (TOF) Time of flight path length constant 600 cm within + 3-5 %. Burst, channel widths are 0.5 micro-sec + each. + (SLODT) Slowing-down-time neutron spectrometer +DETECTOR (SCIN) Stilbene crystal scintillation counter +HISTORY (19970807T) + + Compiled at the center - CJD + + + (20110519A) M.M. Subent 003 was added. +ENDBIB 16 NOCOMMON 0 0 -ENDSUBENT 18 -SUBENT 41272002 970807 20050926 0000 -BIB 2 4 +ENDSUBENT 19 +SUBENT 41272002 20110519 20111003 20110930 4153 +BIB 4 7 REACTION 1(5-B-10(N,0),,EN) 2(5-B-10(N,EL),,WID) 3(5-B-10(N,A),,WID) -HISTORY (970807T) * * CONVERTED FROM SUBENT 80520002 -ENDBIB 4 +ANALYSIS Data deduced from total cross section of B-10 in the + same energy interval . +STATUS (TABLE) Text, page 13 of J,ZET,33,(1),9,1957 . +HISTORY (19970807T) * * Converted from SUBENT 80520002 +ENDBIB 7 NOCOMMON 0 0 DATA 3 1 DATA-APRX 1DATA-APRX 2DATA-APRX 3 KEV KEV KEV 2.5000E+02 2.0000E+02 4.0000E+02 ENDDATA 3 -ENDSUBENT 12 -ENDENTRY 2 +ENDSUBENT 15 +SUBENT 41272003 20110519 20111003 20110930 4153 +BIB 4 13 +REACTION ((3-LI-6(N,T)2-HE-4,,SIG)/(5-B-10(N,X)2-HE-4,,SIG)) +STATUS (PENTZ) From the text file at http://www-nds.iaea.org/ + standards/LastResults/GMDATA-21Oct04.CRD + Relative ratio of Li6/B-10 in arbitrary units is on: + Fig.11 of C,55GENEVA ( as preliminary measurement, + from 20 eV to 5 keV energy range, constant within 2%), + Fig.4 of J,ZET,33,(1),9,1957 (from 0.4 keV to 300 keV + constant within 3 % at En < 25 keV). +ERR-ANALYS (ERR-S) Statistical uncertainty + (ERR-1) Other systematical uncertainties + (ERR-2) Uncertainty of detector efficiency + (ERR-3) Uncertainty of background correction. +HISTORY (20110519C) M.M. +ENDBIB 13 +COMMON 3 3 +ERR-S ERR-1 ERR-3 +PER-CENT PER-CENT PER-CENT + 3.0 3.0 1.0 +ENDCOMMON 3 +DATA 3 39 +EN DATA ERR-2 +MEV NO-DIM PER-CENT + .9000E-05 .2451E+00 .2 + .3946E-03 .2462E+00 .2 + .4178E-03 .2482E+00 .2 + .4357E-03 .2451E+00 .2 + .4627E-03 .2501E+00 .2 + .4878E-03 .2513E+00 .2 + .5526E-03 .2462E+00 .2 + .5743E-03 .2501E+00 .2 + .6163E-03 .2421E+00 .2 + .6509E-03 .2532E+00 .2 + .6822E-03 .2451E+00 .2 + .7398E-03 .2451E+00 .2 + .7779E-03 .2524E+00 .2 + .8384E-03 .2451E+00 .2 + .9006E-03 .2482E+00 .2 + .1008E-02 .2482E+00 .2 + .1113E-02 .2513E+00 .2 + .1184E-02 .2441E+00 .3 + .1318E-02 .2482E+00 .3 + .1420E-02 .2411E+00 .3 + .1535E-02 .2543E+00 .3 + .1678E-02 .2451E+00 .3 + .1827E-02 .2451E+00 .3 + .2033E-02 .2462E+00 .3 + .2232E-02 .2513E+00 .3 + .2487E-02 .2482E+00 .3 + .2759E-02 .2451E+00 .3 + .3044E-02 .2451E+00 .3 + .3297E-02 .2553E+00 .3 + .3762E-02 .2472E+00 .4 + .4393E-02 .2482E+00 .4 + .5049E-02 .2553E+00 .4 + .6048E-02 .2472E+00 .5 + .6889E-02 .2553E+00 .5 + .8684E-02 .2482E+00 .6 + .1037E-01 .2543E+00 .6 + .1289E-01 .2462E+00 .8 + .1782E-01 .2524E+00 .3 + .2625E-01 .2472E+00 .3 +ENDDATA 41 +ENDSUBENT 63 +ENDENTRY 3 diff --git a/exforall/412/41284.x4 b/exforall/412/41284.x4 index 497d8b6f8..78d0130a6 100644 --- a/exforall/412/41284.x4 +++ b/exforall/412/41284.x4 @@ -1,43 +1,53 @@ -ENTRY 41284 980223 20050926 0000 -SUBENT 41284001 980223 20050926 0000 -BIB 10 21 -TITLE .RESONANCE PARAMETERS OF CS-133 AND CS-134 ISOTOPES IN - THE ENERGY RANGE UP TO 400 EV -AUTHOR (V.A.ANUFRIEV,T.S.BELANOVA,S.E.BABICH,YU.S.ZAMYATHIN, - A.G.KOLESOV,E.I.SHKOKOV,S.M.KALEBIN,B.S.ARTAMONOV, - R.N.IVANOV) -INSTITUTE (4RUSNIR) ANUFRIEV, BABICH, ZAMYATNIN, SHKOKOV, - KALEBIN, ARTAMONOV, IVANOV - (4RUSFEI) BELANOVA, KOLESOV -REFERENCE (J,AE,43,201,7709) -FACILITY (REAC,4RUSNIR) SM-2 REACTOR - (CHOPS,4RUSNIR) REACTOR CHOPPER -METHOD (TOF) TIME OF FLIGHT WITH A 70 NSEC/M RESOLUTION -DETECTOR (GELI) GERMANIUM-LITHIUM DETECTOR -ANALYSIS (AREA,SHAPE) AREA ANALYSIS USED TO OBTAIN RESONANCE - PARAMETERS ABOVE 50 EV AND SHAPE ANALYSIS - USED BELOW 50 EV -ERR-ANALYS (ERR-T) TOTAL ERROR - (ERR-S) MAX STATISTICAL UNCERTAINTY 1.5 PC - (ERR-1) MIN STATISTICAL UNCERTAINTY 0.5 PC - (ERR-2) UNCERTAINTY IN NEUTRON BACKGROUND: 4 PC -HISTORY (980223C) + + COMPILED AT THE CENTER - CJD + + -ENDBIB 21 -COMMON 4 3 -EN-RSL ERR-S ERR-1 ERR-2 -NSEC/M PER-CENT PER-CENT PER-CENT - 70. 1.5 0.5 4.0 +ENTRY 41284 20110705 20111003 20110930 4153 +SUBENT 41284001 20110705 20111003 20110930 4153 +BIB 11 29 +TITLE .Resonance parameters of Cs-133 and Cs-134 isotopes at + energies up to 400 eV . +AUTHOR (V.A.Anufriev,T.S.Belanova,S.E.Babich,Yu.S.Zamyathin, + A.G.Kolesov,E.I.Shkokov,S.M.Kalebin,B.S.Artamonov, + R.N.Ivanov) +INSTITUTE (4RUSNIR) Anufriev, Babich, Zamyatnin, Shkokov, + Kalebin, Artamonov, Ivanov + (4RUSFEI) Belanova, Kolesov +REFERENCE (J,AE,43,(3),201,197709) + (J,SJA,43,(3),828,1977) Engl. translation of J,AE,43 . + #doi:10.1007/BF01119050 +FACILITY (REAC,4RUSNIR) SM-2 reactor + (CHOPS,4RUSNIR) Reactor chopper +METHOD (TOF) Time of flight with a 70 nsec/m resolution + (TRN) Transmission. +DETECTOR (GELI) Germanium-lithium detector +ANALYSIS (AREA,SHAPE) Area analysis used to obtain resonance + parameters above 50 eV and shape analysis + used below 50 eV +ERR-ANALYS (ERR-T) Total error + (ERR-S,0.5,1.5) Statistical uncertainty + (ERR-2,,4.) Max. uncertainty in neutron background. +STATUS (DEP,40468001) In 40468 - previous publication, + data for some samples. +HISTORY (19980223C) + + Compiled at the center - CJD + + + (20110705A) M.M. Upper -> lower case correction. + Dates were corrected for 4-digits year. + Ref. J,SJA was added. + BIB information was added. +ENDBIB 29 +COMMON 1 3 +EN-RSL +NSEC/M + 70. ENDCOMMON 3 -ENDSUBENT 28 -SUBENT 41284002 980223 20050926 0000 -BIB 3 6 +ENDSUBENT 36 +SUBENT 41284002 20110705 20111003 20110930 4153 +BIB 4 8 REACTION 1(55-CS-133(N,0),,EN) 2(55-CS-133(N,EL),,WID,,2G) 3(55-CS-133(N,TOT),,WID) -SAMPLE .POWDERED CESIUM SAMPLES. CS-133 THICKNESSES ARE - 1.767E+21, 9.514E+21, 3.61E+22 ATOMS/CM2 -HISTORY (980223T) CONVERTED FROM SUBENT 87012002 -ENDBIB 6 +SAMPLE Powdered CsCl samples. Cs-133 thicknesses are + 1.767E+21, 9.514E+21, 3.61E+22 atoms/cm**2 +STATUS (TABLE) Table 1 of J,AE,43,(3),201,1977. + (DEP,40468002) In 40468002- data for one sample. +HISTORY (19980223T) Converted from SUBENT 87012002 +ENDBIB 8 NOCOMMON 0 0 DATA 6 20 DATA 1ERR-T 1DATA 2ERR-T 2DATA 3ERR-T 3 @@ -63,76 +73,88 @@ EV EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV 3.7300E+02 1.6000E+00 8.0000E+00 4.0000E+00 3.9770E+02 1.8000E+00 3.5100E+02 6.4000E+01 ENDDATA 22 -ENDSUBENT 33 -SUBENT 41284003 980223 20050926 0000 -BIB 4 5 +ENDSUBENT 35 +SUBENT 41284003 20110705 20111003 20110930 4153 +BIB 4 6 REACTION (55-CS-133(N,0),,D) -SAMPLE .POWDERED CESIUM SAMPLES. CS-133 THICKNESSES ARE - 1.767E+21, 9.514E+21, 3.61E+22 ATOMS/CM2 +SAMPLE .Powdered CsCl Samples. Cs-133 thicknesses are + 1.767E+21, 9.514E+21, 3.61E+22 atoms/cm**2 STATUS (DEP,41284002) -HISTORY (980223T) CONVERTED FROM SUBENT 87012003 -ENDBIB 5 + (TABLE) Text, page 201 of J,AE,43,(3),201,1977. +HISTORY (19980223T) Converted from SUBENT 87012003 +ENDBIB 6 NOCOMMON 0 0 DATA 5 1 -EN-MIN EN-MAX DATA ERR-T MOMENTUM L +EN-RES-MIN EN-RES-MAX DATA ERR-T MOMENTUM L EV EV EV EV NO-DIM 1.0000E+00 4.0000E+02 1.6300E+01 2.3000E+00 0.0000E+00 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41284004 980223 20050926 0000 -BIB 4 5 +ENDSUBENT 14 +SUBENT 41284004 20110705 20111003 20110930 4153 +BIB 4 6 REACTION (55-CS-133(N,EL),,STF) -SAMPLE .POWDERED CESIUM SAMPLES. CS-133 THICKNESSES ARE - 1.767E+21, 9.514E+21, 3.61E+22 ATOMS/CM2 +SAMPLE .Powdered CsCl Samples. Cs-133 thicknesses are + 1.767E+21, 9.514E+21, 3.61E+22 atoms/cm**2 STATUS (DEP,41284002) -HISTORY (980223T) CONVERTED FROM SUBENT 87012003 -ENDBIB 5 + (TABLE) Text, page 201 of J,AE,43,(3),201,1977. +HISTORY (19980223T) Converted from SUBENT 87012003 +ENDBIB 6 NOCOMMON 0 0 DATA 5 1 -EN-MIN EN-MAX DATA ERR-T MOMENTUM L +EN-RES-MIN EN-RES-MAX DATA ERR-T MOMENTUM L EV EV NO-DIM NO-DIM NO-DIM 1.0000E+00 4.0000E+02 1.0200E-04 4.3000E-05 0.0000E+00 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41284005 980223 20050926 0000 -BIB 3 5 -REACTION (55-CS-133(N,EL),,WID/RED,,2G/AV) AVERAGED OVER - RESONANCES -SAMPLE .POWDERED CESIUM SAMPLES. CS-133 THICKNESSES ARE - 1.767E+21, 9.514E+21, 3.61E+22 ATOMS/CM2 +ENDSUBENT 14 +SUBENT 41284005 20110705 20111003 20110930 4153 +BIB 3 6 +REACTION (55-CS-133(N,EL),,WID/RED,,2G/AV) Averaged over + resonances +SAMPLE .Powdered CsCl samples. Cs-133 thicknesses are + 1.767E+21, 9.514E+21, 3.61E+22 atoms/cm**2 STATUS (DEP,41284002) -ENDBIB 5 + (TABLE) Text, page 201 of J,AE,43,(3),201,1977. +ENDBIB 6 NOCOMMON 0 0 DATA 5 1 -EN-MIN EN-MAX DATA ERR-T MOMENTUM L +EN-RES-MIN EN-RES-MAX DATA ERR-T MOMENTUM L EV EV EV EV NO-DIM 1.0000E+00 4.0000E+02 3.6700E-03 1.4400E-03 0.0000E+00 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41284006 980223 20050926 0000 -BIB 5 6 +ENDSUBENT 14 +SUBENT 41284006 20110705 20111003 20110930 4153 +BIB 6 9 REACTION (55-CS-133(N,ABS),,RI,,,DERIV) -SAMPLE .POWDERED CESIUM SAMPLES. CS-133 THICKNESSES ARE - 1.767E+21, 9.514E+21, 3.61E+22 ATOMS/CM2 -COMMENT MINIMUM ENERGY ASSUMED BY THE 87012 COMPILER -STATUS (DEP,41284002) -HISTORY (980223T) CONVERTED FROM SUBENT 87012004 -ENDBIB 6 +SAMPLE .Powdered CsCl samples. Cs-133 thicknesses are + 1.767E+21, 9.514E+21, 3.61E+22 atoms/cm**2 +COMMENT Minimum energy assumed by the 87012 compiler as 0.5 eV. +ANALYSIS Total resonance integral RI was calculated by + resonances of Subent 002. +STATUS (DEP,41284002) Calculated using resonances of Subent 2. + (TABLE) Text, page 201 of J,AE,43,(3),201,1977. +HISTORY (19980223T) Converted from SUBENT 87012004 +ENDBIB 9 NOCOMMON 0 0 DATA 3 1 EN-MIN DATA ERR-T EV B B 5.0000E-01 4.0400E+02 9.0000E+01 ENDDATA 3 -ENDSUBENT 14 -SUBENT 41284007 980223 20050926 0000 -BIB 3 5 +ENDSUBENT 17 +SUBENT 41284007 20110705 20111003 20110930 4153 +BIB 5 11 REACTION 1(55-CS-134(N,0),,EN) 2(55-CS-134(N,EL),,WID,,2G) 3(55-CS-134(N,TOT),,WID) -SAMPLE THE SAMPLE INCLUDED 97.6% CS-133 AND 2.29% CS-134 -HISTORY (980223T) CONVERTED FROM SUBENT 87012005 -ENDBIB 5 +SAMPLE The sample included 97.6% Cs-133 and 2.29% Cs-134 +COMMENT Resonance 42.13 +- 0.14 eV with 2gGn=1.14+-0.26 meV is + given in Table 2 under question, as may be of level of + Cs-135 or Cs-137. +STATUS (TABLE) Table 2 of J,AE,43,(3),201,1977. + (DEP,40468003) This data supersede ones of 40468.003 . +HISTORY (19980223T) Converted from SUBENT 87012005 + (20110605A) M.M.Comment was added . +ENDBIB 11 NOCOMMON 0 0 DATA 6 6 DATA 1ERR-T 1DATA 2ERR-T 2DATA 3ERR-T 3 @@ -144,62 +166,68 @@ EV EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV 1.5350E+02 7.0000E-01 9.6000E+00 3.9000E+00 1.7100E+02 1.0000E+00 1.0300E+01 4.2000E+00 ENDDATA 8 -ENDSUBENT 18 -SUBENT 41284008 980223 20050926 0000 -BIB 4 4 +ENDSUBENT 24 +SUBENT 41284008 20110705 20111003 20110930 4153 +BIB 4 5 REACTION (55-CS-134(N,0),,D) -SAMPLE THE SAMPLE INCLUDED 2.29% CS-134 +SAMPLE The sample included 2.29% Cs-134 STATUS (DEP,41284007) -HISTORY (980223T) CONVERTED FROM SUBENT 87012006 -ENDBIB 4 + (TABLE) Text, page 202 of J,AE,43,(3),201,1977. +HISTORY (19980223T) Converted from SUBENT 87012006 +ENDBIB 5 NOCOMMON 0 0 DATA 5 1 -EN-MIN EN-MAX DATA ERR-T MOMENTUM L +EN-RES-MIN EN-RES-MAX DATA ERR-T MOMENTUM L EV EV EV EV NO-DIM 1.2270E+01 1.7100E+02 2.7000E+01 7.5000E+00 0.0000E+00 ENDDATA 3 -ENDSUBENT 12 -SUBENT 41284009 980223 20050926 0000 -BIB 4 4 +ENDSUBENT 13 +SUBENT 41284009 20110705 20111003 20110930 4153 +BIB 4 5 REACTION (55-CS-134(N,EL),,STF) -SAMPLE THE SAMPLE INCLUDED 2.29% CS-134 +SAMPLE The sample included 2.29% Cs-134 STATUS (DEP,41284007) -HISTORY (980223T) CONVERTED FROM SUBENT 87012006 -ENDBIB 4 + (TABLE) Text, page 202 of J,AE,43,(3),201,1977. +HISTORY (19980223T) Converted from SUBENT 87012006 +ENDBIB 5 NOCOMMON 0 0 DATA 5 1 -EN-MIN EN-MAX DATA ERR-T MOMENTUM L +EN-RES-MIN EN-RES-MAX DATA ERR-T MOMENTUM L EV EV NO-DIM NO-DIM NO-DIM 1.2270E+01 1.7100E+02 9.0000E-06 6.0000E-06 0.0000E+00 ENDDATA 3 -ENDSUBENT 12 -SUBENT 41284010 980223 20050926 0000 -BIB 5 5 +ENDSUBENT 13 +SUBENT 41284010 20110705 20111003 20110930 4153 +BIB 5 6 REACTION (55-CS-134(N,ABS),,RI,,,DERIV) -SAMPLE THE SAMPLE INCLUDED 2.29% CS-134 -COMMENT MINIMUM ENERGY ASSUMED BY THE 87012 COMPILER +SAMPLE The sample included 2.29% Cs-134 +COMMENT Minimum energy assumed by the 87012 compiler STATUS (DEP,41284007) -HISTORY (980223T) CONVERTED FROM SUBENT 87012007 -ENDBIB 5 + (TABLE) Text, page 202 of J,AE,43,(3),201,1977. +HISTORY (19980223T) Converted from SUBENT 87012007 +ENDBIB 6 NOCOMMON 0 0 DATA 3 1 EN-MIN DATA ERR-T EV B B 5.0000E-01 2.2000E+01 1.2000E+01 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41284011 980223 20050926 0000 -BIB 3 4 -REACTION (55-CS-134(N,EL),,WID/RED,,2G/AV) AVERAGED OVER - RESONANCES -SAMPLE THE SAMPLE INCLUDED 2.29% CS-134 +ENDSUBENT 14 +SUBENT 41284011 20110705 20111003 20110930 4153 +BIB 4 7 +REACTION (55-CS-134(N,EL),,WID/RED,,2G/AV) Averaged over + resonances +SAMPLE The sample included 2.29% CS-134 +ANALYSIS Total resonance integral RI was calculated by + resonances of Subent 007. STATUS (DEP,41284007) -ENDBIB 4 + (TABLE) Text, page 202 of J,AE,43,(3),201,1977. +ENDBIB 7 NOCOMMON 0 0 DATA 5 1 -EN-MIN EN-MAX DATA ERR-T MOMENTUM L +EN-RES-MIN EN-RES-MAX DATA ERR-T MOMENTUM L EV EV EV EV NO-DIM 1.0000E+00 4.0000E+02 4.9000E-04 2.8000E-04 0.0000E+00 ENDDATA 3 -ENDSUBENT 12 +ENDSUBENT 15 ENDENTRY 11 diff --git a/exforall/413/41318.x4 b/exforall/413/41318.x4 index 1ff50b410..27abe698f 100644 --- a/exforall/413/41318.x4 +++ b/exforall/413/41318.x4 @@ -1,54 +1,78 @@ -ENTRY 41318 19990111 19990429 20050926 0000 -SUBENT 41318001 19990111 19990429 20050926 0000 -BIB 12 22 -TITLE .MEASUREMENT OF THE N-GAMMA TO NF CROSS-SECTIONS - RATION FOR NP-237(NG)/PU-239(NF) IN TWO FAST CRITICAL - ASSEMBLIES -AUTHOR (V.A.DULIN,I.V MIKHAYLOV,A.M.TSIBULYA) +ENTRY 41318 20110604 20111003 20110930 4153 +SUBENT 41318001 20110604 20111003 20110930 4153 +BIB 13 43 +TITLE Measurement of the ratio of the average Np-237 capture + cross-section to the Pu-239 fission cross-section in + two BFS critical assemblies +AUTHOR (V.A.Dulin) INSTITUTE (4RUSFEI) -REFERENCE (J,AE,84,(6),541,199806) MAIN REFERENCE, DATA ARE GIVE -FACILITY (REAC) FAST CRITICAL ASSEMBLY BFS-1 WITH DIFFERENT - MODIFICATIONS OF REACTOR CORE -MONITOR .ABSOLUTE MEASUREMENTS +REFERENCE (J,AE,84,(6),541,199806) Main reference, data are given + (J,AE/T,84,(6),407,1998) Engl.translation of J,AE,84 . + #doi:10.1007/BF02413902 +FACILITY (REAC) Fast critical assembly BFS-1 with different + modifications of reactor core +MONITOR .Absolute measurements METHOD (ACTIV) -DETECTOR (FISCH) FOR FISSION CROSS-SECTION MEASUREMENTS - (GELI) FOR N-GAMMA CS MEASUREMENTS +DETECTOR (FISCH) For fission cross-section measurements + (GELI) For n-gamma cs measurements + For calibration - standard sources of absolute activity + with 1.2-1.4% uncertainty were used. + Lead layer of 12.1 mm thickness to decrease + gamma-counting rate. + Without Pb - absolute efficiency was defined by Cs-137, + Co-60, Eu-152 (779, 964 keV) and was straight line in + double-logarithmic scale. With Pb - efficiency was + almost independent from energy. DECAY-DATA (93-NP-238,2.118D,DG,984.0,0.278, DG,1027.0,0.300) + 0.278+-0.009; 0.300+-0.008 (94-PU-239,24110.0YR) -SAMPLE .PU-239 SAMPLE AS THIN FILM ON THE FISSION CHAMBER - ELECTRODE, QUANTITY OF PU-239 IS (1.954+-.016)E-7 - MOLE, PU-240 ADMIXTURE IS 0.13+-0.03 PC - .NP SAMPLE AS OXIDE DISK OF NP-O2, DIAMETER 7 MM,MASS - 24-30 MILLIGRAM. -ERR-ANALYS (ERR-T) TOTAL ERROR, COMPOSITION IS NOT SPECIFIED -HISTORY (19990111C) + + COMPILED AT THE CJD + + -ENDBIB 22 +SAMPLE .Pu-239 sample as thin film on the fission chamber + electrode, quantity of Pu-239 is (1.954+-.016)E-7 + mole, Pu-240 admixture is 0.13+-0.03 % + .Np sample as oxide disk of Np-O2, Diameter 7 mm,mass + 24-30 milligram. +ERR-ANALYS (ERR-T) Total error. + (ERR-S,0.4,0.7) Statistical uncertainty of detector + efficiency measurement. + (ERR-1) Uncertainty of Np-238 gamma lines absolute + efficiency measurement. +CORRECTION For neutron self-absorption in samples. +HISTORY (19990111C) + + Compiled at the CJD + + + (20110704A) M.M. Upper -> lower case correction. + Ref.J,AE/T was added. + Authors' names I.V.Mikhaylov,A.M.Tsibulya were deleted + as not given in the article. + BIB information was added. +ENDBIB 43 COMMON 1 3 -ERR-S +ERR-1 PER-CENT - 0.7 + 2. ENDCOMMON 3 -ENDSUBENT 29 -SUBENT 41318002 19990111 19990429 20050926 0000 -BIB 4 16 +ENDSUBENT 50 +SUBENT 41318002 20110604 20111003 20110930 4153 +BIB 4 19 REACTION 1((93-NP-237(N,G)93-NP-238,,SIG,,SPA)/ - (94-PU-239(N,F),,SIG,,SPA)) AVERAGED OVER BROAD - NEURTON SPECTRUM + (94-PU-239(N,F),,SIG,,SPA)) averaged over broad + neutron spectrum of BFS 71-2. 2((93-NP-237(N,G)93-NP-238,,SIG,,SPA)/ - (94-PU-239(N,F),,SIG,,SPA)) AVERAGED OVER BROAD - NEURTON SPECTRUM + (94-PU-239(N,F),,SIG,,SPA)) Averaged over broad + neutron spectrum of BFS 73-1 3((93-NP-237(N,G)93-NP-238,,SIG,,SPA)/ - (94-PU-239(N,F),,SIG,,SPA)) AVERAGED OVER BROAD - NEURTON SPECTRUM -ANALYSIS 1.REACTOR WITH OXIDE CORE, RELATIVE MEASUREMENTS - 2.REACTOR WITH METALLIC CORE AND NATRIUM HEAT-TRANSFER - AGENT, RELATIVE MEASUREMENTS - 3.REACTOR WITH METALLIC CORE AND NATRIUM HEAT-TRANSFER - AGENT, ABSOLUTE MEASUREMENTS -INC-SPECT .NEUTRON SPECTRUM OF THE FAST REACTOR'S ACTIVE CORE -STATUS (TABLE) DATA ARE TAKEN FROM TABLE 5 OF THE MAIN REF. -ENDBIB 16 + (94-PU-239(N,F),,SIG,,SPA)) Averaged over broad + neutron spectrum of BFS 73-1 +ANALYSIS 1.Reactor with oxide core, relative measurements, + BNAB thermal constants were used. + 2.Reactor with metallic core and sodium heat-transfer + agent, relative measurements, + BNAB thermal constants were used. + Defined as (0.546*0.214)/0.207=0.563 . + 3.Reactor with metallic core and sodium heat-transfer + agent, absolute measurements +INC-SPECT .Neutron spectrum of the fast reactor's active core +STATUS (TABLE) Table 5 of J,AE,84,(6),541,1998. +ENDBIB 19 COMMON 1 3 EN-DUMMY EV @@ -59,14 +83,14 @@ DATA 1ERR-T 1DATA 2ERR-T 2DATA 3ERR-T 3 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 0.584 0.19 0.563 0.018 0.546 0.025 ENDDATA 3 -ENDSUBENT 28 -SUBENT 41318003 19990111 19990429 20050926 0000 +ENDSUBENT 31 +SUBENT 41318003 20110604 20111003 20110930 4153 BIB 3 5 REACTION ((93-NP-237(N,G)93-NP-238,,SIG,,MXW)/ - (94-PU-239(N,F),,SIG,,MXW)) AVERAGED THERMAL - NEURTON SPECTRUM -INC-SPECT .THERMAL COLUMN OF THE FAST REACTOR -STATUS DATA ARE TAKEN FROM THE MAIN REFERENCE + (94-PU-239(N,F),,SIG,,MXW)) Averaged thermal + neutron spectrum of BFS 73-1, thermal column. +INC-SPECT .Thermal column of the fast reactor +STATUS (TABLE) Table 4 of J,AE,84,(6),541,1998. ENDBIB 5 NOCOMMON 0 0 DATA 3 1 diff --git a/exforall/413/41322.x4 b/exforall/413/41322.x4 index b3f7b4dab..14997c0a1 100644 --- a/exforall/413/41322.x4 +++ b/exforall/413/41322.x4 @@ -1,18 +1,19 @@ -ENTRY 41322 20090817 20091127 20091127 4147 -SUBENT 41322001 20090817 20091127 20091127 4147 -BIB 12 51 +ENTRY 41322 20110701 20111003 20110930 4153 +SUBENT 41322001 20110701 20111003 20110930 4153 +BIB 12 54 INSTITUTE (4RUSFEI) REFERENCE (J,AE,85,(1),51,199807) Main reference. Data and correlation matrix of delayed neutron parameters . (J,YK,1997,(1-2),18,199708) Data for n-energy 1.154 MeV end errors' structure are given . (C,95OBNIN,295,199510) Preliminary Data + (J,AE/T,85,(1),479,1998) Eng.transl. of J,AE,85,(1),51 + #doi:10.1007/BF02358784 AUTHOR (V.M.Piksaykin,Yu.F.Balakshev,S.G.Isaev,L.E.Kazakov, G.G.Korolev,V.I.Mil'shin) -TITLE Measurements of energy dependence of relative abun- - dances of delayed neutrons and group periods - of their precursors from fast neutron induced fission - of 237-Np. +TITLE Measurement of the energy dependence of the parameters + of delayed neutrons accompanying fission of Np-237 by + fast neutrons . FACILITY (VDG) Electrostatic cascade generator KG-2.5 DETECTOR (D4PI) Boron counter SNM-11 as assemblage of 30 counters distributed in polyethylene moderator - @@ -42,7 +43,7 @@ ERR-ANALYS (ERR-S) Error due to fission counting statistics of counts to fission fragments counts ratio (ERR-8) Error due to delayed neutron from impurities of U-235. - Error structure is taken from REFERENCE 3. + Error structure is taken from C,95OBNIN. COVARIANCE (COVAR) Covariance matrix may by obtained from the first author by e-mail PIKSA@IPPE.RSSI.RU STATUS (COREL,41291001) Final data for Np-237 at 1.154 MeV in @@ -52,7 +53,9 @@ HISTORY (19990125C) + + Compiled at CJD (20090817A) M.M. Misprint in Title was corrected. Dates were corrected for 4-digits year. Free text was corrected to be human-readable. -ENDBIB 51 + (20110630A) M.M. J,AE/T,85,(1),1998 was added. + Correlation matrix was added in Subent 003. +ENDBIB 54 COMMON 8 6 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 ERR-7 ERR-8 @@ -61,16 +64,16 @@ PER-CENT PER-CENT 0.7 0.6 1. 0.05 0.01 0.1 0.6 0.06 ENDCOMMON 6 -ENDSUBENT 61 -SUBENT 41322002 20090817 20091127 20091127 4147 +ENDSUBENT 64 +SUBENT 41322002 20110701 20111003 20110930 4153 BIB 3 7 REACTION ((93-NP-237(N,F),DL/GRP,NU)/ (93-NP-237(N,F),DL,NU)) SAMPLE Np-O2 oxide powder, density 7 gram/cm**3, packed in stainless-steel capsule placed in titanium container. Sample weight is 2.2810 gram -STATUS (TABLE) Table 1 of main reference- for 1.008 MeV . - Table 3 of main reference - for all energies. +STATUS (TABLE) Table 3 and Table 1 (first two data lines) + of J,AE,85,(1),51,1998. ENDBIB 7 COMMON 1 3 ERR-S @@ -124,16 +127,39 @@ MEV MEV SEC SEC NO-DIM NO-DIM 4.719 0.205 0.206 0.010 0.033 0.002 ENDDATA 44 ENDSUBENT 60 -SUBENT 41322003 20090817 20091127 20091127 4147 -BIB 4 7 +SUBENT 41322003 20110701 20111003 20110930 4153 +BIB 5 30 REACTION ((93-NP-237(N,F),DL/GRP,NU)/ (93-NP-237(N,F),DL,NU)) ANALYSIS Data obtained by the summation method SAMPLE Np-O2 oxide powder, density 7 gram/cm3, packed in stainless-steel capsule placed in titanium container. Sample weight is 2.2810 gram. -STATUS (TABLE) Data are taken from Table 1 of main ref. -ENDBIB 7 +COVARIANCE Correlation matrix: + A- intensity of precursors producing, + b- neutron background intensity, + a -relative yield, + T - half-life. + A b a1 T1 a2 T2 a3 T3 a4 T4 a5 T5 + A 1.00 + b 0.01 1. + a1 0. 0. 1. + T1 -.32 -.10 0. 1. + a2 -.35 -.04 0. .75 1. + T2 -.26 .03 0. .06 -.04 1. + a3 -.09 0. 0. .26 .23 .39 1. + T3 -.08 .01 0. .01 -.28 .56 -.09 1. + a4 -.01 -.01 0. .50 .50 .43 -.05 .40 1. + T4 -.52 0. 0. .13 .17 .15 -.33 -.06 .04 1. + a5 .33 0. 0. .09 .09 .08 .02 .05 -.06 .16 1. + T5 -.28 0. 0. .06 .06 .06 .01 .06 -.07 .07 -.01 1. + a6 .11 0. 0. .01 .01 .01 0. 0. 0. .01 -.01 0. + T6 -.03 0. 0. .01 .01 .01 0. 0. 0. .01 -.01 0. + a6 T6 + a6 1. + T6 0. 1. +STATUS (TABLE) Table 1 of J,AE,85,(1),51,1998 . +ENDBIB 30 COMMON 3 3 EN EN-ERR ERR-S MEV MEV PER-CENT @@ -149,23 +175,24 @@ SEC NO-DIM NO-DIM 0.546 0.155 0.040 0.193 0.027 0.012 ENDDATA 8 -ENDSUBENT 24 -SUBENT 41322004 20090817 20091127 20091127 4147 -BIB 3 6 -REACTION (93-NP-237(N,F),DL/GRP,NU,,REL) .Measurements +ENDSUBENT 47 +SUBENT 41322004 20110701 20111003 20110930 4153 +BIB 3 7 +REACTION ((93-NP-237(N,F),DL/GRP,NU)// + (93-NP-237(N,F),DL/GRP,NU)) .Measurements relative to 55 sec group yield SAMPLE .Np-O2 Oxide powder, density 8 gram/cm**3, sample weight is 2. gram -STATUS (PRELM) Data are taken from Table of ref. 3 - (TABLE) -ENDBIB 6 -COMMON 1 3 -EN -MEV - 1.2 +STATUS (PRELM) Preliminary data + (TABLE) Table of C,95OBNIN,295,1995 +ENDBIB 7 +COMMON 2 3 +EN HL-DN +MEV SEC + 1.2 55.69 ENDCOMMON 3 DATA 4 6 -HL HL-ERR DATA ERR-S +HL-NM HL-ERR DATA ERR-S SEC SEC NO-DIM NO-DIM 55.69 0.69 1. 22.21 0.21 8.18 0.31 @@ -174,5 +201,5 @@ SEC SEC NO-DIM NO-DIM 0.77 0.08 3.03 0.62 0.27 0.03 0.49 0.16 ENDDATA 8 -ENDSUBENT 23 +ENDSUBENT 24 ENDENTRY 4 diff --git a/exforall/413/41345.x4 b/exforall/413/41345.x4 index f28898e2b..7a6644850 100644 --- a/exforall/413/41345.x4 +++ b/exforall/413/41345.x4 @@ -1,60 +1,79 @@ -ENTRY 41345 20000125 20000427 20050926 0000 -SUBENT 41345001 20000125 20000427 20050926 0000 -BIB 13 40 +ENTRY 41345 20110630 20111003 20110930 4153 +SUBENT 41345001 20110630 20111003 20110930 4153 +BIB 13 52 TITLE .Determination of the Parameters of the Neutron Reso- - Nances of 149Sm in the Energy Range 15-300 eV -AUTHOR (G.P.GEORGIEV, YU.S.ZAMYATNIN, L.B.PIKEL'NER, - KH.FAIKOV-STANCZYK, YU.V.GRIGOR'EV, G.V.MURADYAN, - N.B.YANEVA) + nances of 149Sm in the Energy Range 15-300 eV +AUTHOR (G.P.Georgiev, Yu.S.Zamyatnin, L.B.Pikel'ner, + Kh.Faikov-Stanczyk, Yu.V.Grigoriev, G.V.Muradyan, + N.B.Yaneva) INSTITUTE (4ZZZDUB) Georgiev, Zamyatnin, Pikel'ner, (3POLLOU) Faikow-Stanczyk (4RUSFEI) Grigor'ev (4RUSKUR) Muradyan (3BULBLA) Yaneva -REFERENCE (J,YK,1999,(1),3,19990701) Main Reference, Data Given - (J,AE,50,394,1981) Experimental Details - (R,JINR-P3-88-555,1988) Experimental Details -FACILITY (REAC,4ZZZDUB) IBR-30 Fast Pulse Reactor of Frank - Neutron Physics Laboratory in Booster Mode 10 Kw - Power, Multiplicity Coeff.=200, Pulse Duration - 4 Microsec, Repetition Rate 100 Hz -METHOD .Method of Gamma Multiplicity Spectrometry Coupled - With - (TOF) Time-Of-Fligt Method, Flight Base is 501.9 M - (COINC) Coincidence of Gamma-Multiplicity and - Neutron'S Flight Time -DETECTOR (NAICR,D4PI) Multisectional 4Pi Scintillation - Detector of the Type "ROMASHKA" Consisting of - 16 Crystalline Sections of NaJ(TL) 122X122x152 mm - (PROPC) Two 3He Counters CHM-17 For Neutron Flux - Monitoring -MONITOR .No Information -SAMPLE .Two Oxide Sm2-O3 Samples with 94.6% Enrichment on - 149Sm,Thicknesses 2.47E-4 Atoms/B and 9.26E-5 Atoms/B - Packed in Aluminium Containers 70 mm Diameter +REFERENCE (J,YK,1999,(1),3,19990701) Main reference, data given +REL-REF (M,,G.V.Muradyan,J,AE,50,(6),394,1981) Exp. Details of + method. + (M,,G.V.Muradyan,J,SJA,50,(6),354,1981) + Engl. translation of J,AE,50,(6),394,1981. + (I,,G.P.Georgiev+,R,JINR-P3-88-555,1988) Exp.details + (I,,N.B.Janeva+,J,NIM/A,313,266,1992) Detector details. +FACILITY (REAC,4ZZZDUB) IBR-30 fast pulse reactor of Frank + Neutron Physics Laboratory in booster mode 10 kW + power, multiplicity coeff.=200, pulse duration + 4 microsec, repetition rate 100 Hz +METHOD .Method of gamma multiplicity spectrometry coupled + with + (TOF) time-of-flight method, flight base is 501.9 m + (COINC) Coincidence of gamma-multiplicity and + neutron's flight time + Neutron scattering was registered by 0.48 MeV + gamma-quanta of B-10(N,ALPHA+GAMMA) reaction. +DETECTOR (NAICR,D4PI) Multisectional 4PI scintillation + detector of the type "ROMASHKA" consisting of + 16 crystalline sections of NaI(Tl) 122X122x152 mm + (PROPC) Two 3He counters CHM-17 for neutron flux + monitoring + (n,gamma)-converter inside detector to register + scattered neutrons by 0.48 MeV gamma-quanta of + B-10(n,alpha+gamma) reaction. +SAMPLE .Two oxide Sm2-O3 samples with 94.6% enrichment on + 149Sm,thicknesses 2.47E-4 atoms/b and 9.26E-5 atoms/b + packed in aluminum containers of 70 mm diameter. INC-SOURCE (REAC) -INC-SPECT .For Detector Stability Monitoring and Recycled - Neutrond Background Attenuation Two Neutron Filters - Were Used - Cadmium 1 mm Thickness and Boron 10 mm - Thickness -ERR-ANALYS (ERR-T) Errors are not Specified, Most Probably - - Total Error +INC-SPECT .For detector stability monitoring and recycled + neutrons background attenuation- two neutron filters + were used - cadmium 1 mm thickness and boron 10 mm + thickness +ERR-ANALYS (ERR-T) Errors are not Specified, most probably - + total error HISTORY (20000125C) + + Compiled at the Centre - CJD + + (20000125U) Last checking has been done. -ENDBIB 40 -NOCOMMON -ENDSUBENT 43 -SUBENT 41345002 20000125 20000427 20050926 0000 -BIB 4 7 -REACTION 1(62-SM-149(N,0),,EN) Resonance Energy - 2(62-SM-149(N,0),,J) Spin of the Resonance - 3(62-SM-149(N,G),,WID) Gamma-Width of the Resonance - 4(62-SM-149(N,EL),,WID) Elastic Width of the Resonance -ANALYSIS (AREA) -FLAG (1.) Most Probable Value of the Spin -STATUS (TABLE) Data Taken from the Table of Main Reference -ENDBIB 7 -NOCOMMON + (20110630A) M.M. Upper -> lower case correction. + BIB information was added. Engl.transl J,SJA was added + References J,AE,50,(6),394,1981; R,JINR-P3-88-555,1988 + were moved in REL-REF. +ENDBIB 52 +NOCOMMON 0 0 +ENDSUBENT 55 +SUBENT 41345002 20110630 20111003 20110930 4153 +BIB 7 14 +REACTION 1(62-SM-149(N,0),,EN) Resonance energy + 2(62-SM-149(N,0),,J) Spin of the resonance + 3(62-SM-149(N,G),,WID) Gamma-width of the resonance + 4(62-SM-149(N,EL),,WID) Elastic width of the resonance +MONITOR (92-U-238(N,F),,EN) + Resonance energies were defined by U-238 standard + resonance energies. +MONIT-REF (,S.F.Mughabghab,B,NEUT.CS 1B,,1984) +ANALYSIS (AREA) Area of resonance peak. +CORRECTION For contribution of capture in scattering (4%) and + scattering in capture (5 - 15 %) + For admixtures of others Sm isotopes in sample. +FLAG (1.) Most probable value of the spin +STATUS (TABLE) Data from the Table of J,YK,1999,(1),3,1999 +ENDBIB 14 +NOCOMMON 0 0 DATA 7 91 DATA 1DATA 2DATA 3ERR-T 3DATA 4ERR-T 4 FLAG @@ -243,17 +262,18 @@ NO-DIM 272.8 4. ENDDATA 186 -ENDSUBENT 198 -SUBENT 41345003 20000125 20000427 20050926 0000 -BIB 2 2 -REACTION (62-SM-149(N,G),,WID,,AV) Averaged Over Resonances -STATUS (DEP,41345002) -ENDBIB 2 -NOCOMMON +ENDSUBENT 205 +SUBENT 41345003 20110630 20111003 20110930 4153 +BIB 2 3 +REACTION (62-SM-149(N,G),,WID,,AV) Averaged over 51 resonances +STATUS (TABLE) Text, page 5, of J,YK,1999,(1),3,1999 + (DEP,41345002) Averaged over 51 resonances. +ENDBIB 3 +NOCOMMON 0 0 DATA 4 1 -EN-MIN EN-MAX DATA ERR-T +EN-RES-MIN EN-RES-MAX DATA ERR-T EV EV EV EV - 15. 272. 7.5E-02 3.E-03 + 25.26 263.2 7.5E-02 3.E-03 ENDDATA 3 -ENDSUBENT 10 +ENDSUBENT 11 ENDENTRY 3 diff --git a/exforall/413/41354.x4 b/exforall/413/41354.x4 index 481824804..d9bc6a579 100644 --- a/exforall/413/41354.x4 +++ b/exforall/413/41354.x4 @@ -1,6 +1,6 @@ -ENTRY 41354 20091214 20100209 20100209 4148 -SUBENT 41354001 20091214 20100209 20100209 4148 -BIB 13 38 +ENTRY 41354 20110629 20111003 20110930 4153 +SUBENT 41354001 20110629 20111003 20110930 4153 +BIB 13 43 TITLE Measurements of Neutron Capture Cross Sections of 234-U and 236-U and Fission Cross Section of 236-U. AUTHOR (G.V.Muradyan, M.A.Voskanyan, L.P.Yastrebova, @@ -12,8 +12,11 @@ REFERENCE ((S,ISINN-7,287,1999)=(S,JINR-E3-99-212,287,1999)) Main Reference ((S,ISINN-7,292,1999)=(S,JINR-E3-99-212,292,1999)) Data For U-234 . + (J,AE,110,(2),100,2011) Data for U-236 confirmed. + (J,AE/T,110,(2),115,2011) Engl.translation of J,AE . + #doi:10.1007/s10512-011-9399-z FACILITY (LINAC,4RUSKUR) Pulsed Linear Electron Accelerator - 'FAKEL', electron pulse duration 60 ns, repetiton + 'FAKEL', electron pulse duration 60 ns, repetition frequency 400 Hz REL-REF (N,,G.V.Muradyan+,J,NSE,90,60,1990) Experimental details . @@ -39,21 +42,26 @@ HISTORY (20000317C) + + Compiled at CJD (20000317U) Last checking has been done. (20091214U) Two references of ISINN-7 were added. BIB and COMMON information was added. -ENDBIB 38 + (20110629A) Ref. J,AE,(2),100,2011 and Engl.translation + were added. +ENDBIB 43 NOCOMMON 0 0 -ENDSUBENT 41 -SUBENT 41354002 20091214 20100209 20100209 4148 -BIB 5 9 +ENDSUBENT 46 +SUBENT 41354002 20110629 20111003 20110930 4153 +BIB 5 12 REACTION (92-U-236(N,G)92-U-237,,SIG,,AV) Averaged over energy interval given in data section SAMPLE -Two identical metallic foil 10 mm diameter enriched on 236-U to 99.845%. Thickness 9.443E-4 atoms/barn REL-REF (A,,Yu.A.Adamchuk+,J,AE,65,356,1988) (D,,A.A.Bergman+,J,YK,1988,(1),396,1988) -ERR-ANALYS Statistical errors < 0.5% for each energy intervals . - Systematic error < 4.% . -STATUS (TABLE) From Table 1 of S,ISINN-7,287,1999 . -ENDBIB 9 +ERR-ANALYS Statistical errors < 0.5% for each energy intervals + excluding 10-21.5 eV. + (ERR-SYS,4.) Systematic error < 4.% . +STATUS (TABLE) From Table 1 of S,ISINN-7,287,1999 + = Table 1 of J,AE,(2),100,2011 . + (COREL,40987002) Measurement by different detector. +ENDBIB 12 NOCOMMON 0 0 DATA 3 10 EN-MIN EN-MAX DATA @@ -69,19 +77,23 @@ EV EV B 900. 1000. 4.21 1000. 2000. 2.47 ENDDATA 12 -ENDSUBENT 26 -SUBENT 41354003 20091214 20100209 20100209 4148 -BIB 4 9 -REACTION (92-U-236(N,G)92-U-237,,SIG,,AV) Weighted over 1/En +ENDSUBENT 29 +SUBENT 41354003 20110629 20111003 20110930 4153 +BIB 5 13 +REACTION (92-U-236(N,G)92-U-237,,SIG,,EPI) Weighted over 1/En spectrum capture cross-section within energy interval given in data section SAMPLE -Two identical metallic foil 10 mm diameter enriched on 236-U to 99.845%. Thickness 9.443E-4 atoms/barn ERR-ANALYS Statistical errors < 0.5% for each energy intervals excluding 10.0-21.5 eV. - Systematic error < 4.% . + (ERR-SYS,4.) Systematic error < 4.% . STATUS (TABLE) From Table 2 S,ISINN-7,287,1999. -ENDBIB 9 + = Table 2 of J,AE,(2),100,2011 . + (COREL,40987005) Measurement by different detector. +HISTORY (20110629A) AV -> EPI according to the comment of + N.Otsuka (NDS IAEA). +ENDBIB 13 NOCOMMON 0 0 DATA 3 8 EN-MIN EN-MAX DATA @@ -95,24 +107,30 @@ EV EV B 465. 1000. 5.28 1000. 2150. 2.56 ENDDATA 10 -ENDSUBENT 24 -SUBENT 41354004 20091214 20100209 20100209 4148 -BIB 4 7 -REACTION (92-U-236(N,F),,SIG,,AV) Weighted fission cs +ENDSUBENT 28 +SUBENT 41354004 20110629 20111003 20110930 4153 +BIB 6 13 +REACTION (92-U-236(N,F),,SIG,,EPI) Weighted fission cs over energy interval given in data section SAMPLE -Two identical metallic foil 10 mm diameter enriched on 236-U to 99.845%. Thickness 9.443E-4 atoms/barn +MONITOR ((MONIT)92-U-236(N,F),,WID) + Calibration was done by 5.45 eV resonance of + fission width 0.29 milli-eV. ERR-ANALYS (DATA-ERR) Accuracy is about 6 %, does not include normalization error. STATUS (TABLE) From Table 3 of S,ISINN-7,287,1999 -ENDBIB 7 -COMMON 1 3 -DATA-ERR -PER-CENT - 6. + = Table 3 of J,AE,(2),100,2011 . +HISTORY (20110629A) AV -> EPI according to the comment of + N.Otsuka (NDS IAEA). +ENDBIB 13 +COMMON 3 3 +DATA-ERR EN-RES-NRM MONIT +PER-CENT EV MILLI-EV + 6. 5.45 0.29 ENDCOMMON 3 DATA 4 7 -EN-MIN EN-MAX DATA DATA-MIN +EN-MIN EN-MAX DATA DATA-MAX EV EV B B 4.65 10. 4.21 10. 21.5 0.001 @@ -122,7 +140,7 @@ EV EV B B 215. 465. 0.094 465. 1000. 0.085 ENDDATA 9 -ENDSUBENT 25 +ENDSUBENT 31 SUBENT 41354005 20091214 20100209 20100209 4148 BIB 4 10 REACTION (92-U-234(N,G)92-U-235,,SIG,,AV) Weighted over 1/En diff --git a/exforall/413/41374.x4 b/exforall/413/41374.x4 index dda1d1936..4b5aca0cb 100644 --- a/exforall/413/41374.x4 +++ b/exforall/413/41374.x4 @@ -1,139 +1,142 @@ -ENTRY 41374 20000627 20020926 20050926 0000 -SUBENT 41374001 20000627 20020926 20050926 0000 -BIB 13 20 -TITLE .Measurements of the Alfa-Value For 235U, 238U, 239Pu - In the Active Section of the Reactor 'BOR-60' -AUTHOR (V.S.PROKOPENKO, V.YA.GABESKIRIYA, A.V.INCHAGOV, - YU.B.NOVIKOV, V.M.PROKOP'EV, V.V.TIKHOMIROV, - A.P.CHETVERIKOV) +ENTRY 41374 20110624 20111003 20110930 4153 +SUBENT 41374001 20110624 20111003 20110930 4153 +BIB 13 26 +TITLE Measurements of the Alpha-values for U-235, U-238, + Pu-239 in the active zone of the BOR-60 reactor . +AUTHOR (V.S.Prokopenko, V.Ya.Gabeskiriya, A.V.Inchagov, + Yu.B.Novikov, V.M.Prokop'ev, V.V.Tikhomirov, + A.P.Chetverikov) INSTITUTE (4RUSITE) REFERENCE (J,AE,45,(3),230,197809) Main Reference -FACILITY (REAC) Fast Reactor 'BOR-60' -INC-SOURCE (REAC) Inner Core of the Reactor -INC-SPECT .Fast Neutron Spectrum of the Fast Reactor 'BOR-60' + (J,SJA,45,(3),923,1978) Engl.transl. of J,AE,(3),230 . + #doi:10.1007/BF01117281 +FACILITY (REAC) Fast reactor 'BOR-60' +INC-SOURCE (REAC) Inner core of the reactor +INC-SPECT .Fast neutron spectrum of the fast reactor 'BOR-60' METHOD (MASSP) MONITOR ((MONIT1)92-U-235(N,F)60-ND-145,CUM,FY,,FST) ((MONIT2)94-PU-239(N,F)60-ND-146,CUM,FY,,FST) -MONIT-REF (,F.E.LISMAN,J,NSE,42,(2),191,1970) -ERR-ANALYS (ERR-T) Total Error - (ERR-1) Error of the Experiment - (ERR-2) Error of the Standard Constants -STATUS (TABLE) From the Table of Main Reference + Yields of sum of isotopes were used +MONIT-REF (13270001,F.E.Lisman,J,NSE,42,(2),191,1970) +ERR-ANALYS (ERR-T) Total error of 95% confidence interval. + (ERR-1) Error of the experiment + (ERR-2) Error of the standard constants +STATUS (TABLE) From the Table of J,AE,45,(3),230,1978 HISTORY (20000627C) + + Compiled at the Centre - CJD + + - (20020214U) USSUE NUMBER CORRECTED -ENDBIB 20 + (20020214U) Issue number corrected + (20110624A) Engl. translation of J,AE was added. + Upper->lower case correction. + REACTIONs were corrected: ABS),,ALF was added.. +ENDBIB 26 COMMON 5 3 EN-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR EV PC/FIS PC/FIS PC/FIS PC/FIS 1.E+06 6.85 0.2 5.56 0.12 ENDCOMMON 3 -ENDSUBENT 27 -SUBENT 41374002 20000627 20010329 20050926 0000 -BIB 2 4 -REACTION ((92-U-235(N,G)92-U-236,,SIG,,FST)/ - (92-U-235(N,F),,SIG,,FST)) -SAMPLE .Uranium Dioxide U-O2, Mass 5 Milligram in - Cylindrical Stainless Steel Capsule -ENDBIB 4 -NOCOMMON +ENDSUBENT 33 +SUBENT 41374002 20110624 20111003 20110930 4153 +BIB 2 3 +REACTION (92-U-235(N,ABS),,ALF,,FST) +SAMPLE .Uranium dioxide U-O2, mass 5 milligram in + cylindrical stainless steel capsule +ENDBIB 3 +NOCOMMON 0 0 DATA 4 1 DATA ERR-1 ERR-2 ERR-T NO-DIM PER-CENT PER-CENT PER-CENT 0.197 3.2 3. 4.4 ENDDATA 3 -ENDSUBENT 12 -SUBENT 41374003 20000627 20010329 20050926 0000 -BIB 2 4 -REACTION ((94-PU-239(N,G)94-PU-240,,SIG,,FST)/ - (94-PU-239(N,F),,SIG,,FST)) -SAMPLE .Plutonium Dioxide Pu-O2, Mass 5 Milligram in - Cylindrical Stainless Steel Capsule -ENDBIB 4 -NOCOMMON +ENDSUBENT 11 +SUBENT 41374003 20110624 20111003 20110930 4153 +BIB 2 3 +REACTION (94-PU-239(N,ABS),,ALF,,FST) +SAMPLE .Plutonium dioxide Pu-O2, mass 5 milligram in + cylindrical stainless steel capsule +ENDBIB 3 +NOCOMMON 0 0 DATA 4 1 DATA ERR-1 ERR-2 ERR-T NO-DIM PER-CENT PER-CENT PER-CENT 0.104 4.1 2.2 4.7 ENDDATA 3 -ENDSUBENT 12 -SUBENT 41374004 20000627 20010329 20050926 0000 +ENDSUBENT 11 +SUBENT 41374004 20110624 20111003 20110930 4153 BIB 2 4 REACTION ((94-PU-239(N,G)94-PU-240,,SIG,,FST)/ (92-U-235(N,G)92-U-236,,SIG,,FST)) -SAMPLE .Plutonium Dioxide Pu-O2, Mass 5 Milligram in - Cylindrical Stainless Steel Capsule +SAMPLE .Plutonium dioxide Pu-O2, mass 5 milligram in + cylindrical stainless steel capsule ENDBIB 4 -NOCOMMON +NOCOMMON 0 0 DATA 4 1 DATA ERR-1 ERR-2 ERR-T NO-DIM PER-CENT PER-CENT PER-CENT 0.675 4.6 0.12 4.6 ENDDATA 3 ENDSUBENT 12 -SUBENT 41374005 20000627 20010329 20050926 0000 +SUBENT 41374005 20110624 20111003 20110930 4153 BIB 2 4 REACTION ((94-PU-239(N,F),,SIG,,FST)/ (92-U-235(N,F),,SIG,,FST)) -SAMPLE .Plutonium Dioxide Pu-O2, Mass 5 Milligram in - Cylindrical Stainless Steel Capsule +SAMPLE .Plutonium dioxide Pu-O2, mass 5 milligram in + cylindrical stainless steel capsule ENDBIB 4 -NOCOMMON +NOCOMMON 0 0 DATA 4 1 DATA ERR-1 ERR-2 ERR-T NO-DIM PER-CENT PER-CENT PER-CENT 1.29 2.4 3.6 4.3 ENDDATA 3 ENDSUBENT 12 -SUBENT 41374006 20000627 20010329 20050926 0000 +SUBENT 41374006 20110624 20111003 20110930 4153 BIB 2 4 REACTION ((92-U-238(N,G)92-U-239,,SIG,,FST)/ (92-U-235(N,F),,SIG,,FST)) -SAMPLE .Uranium Dioxide U-O2, Mass 50 Milligram in - Cylindrical Stainless Steel Capsule +SAMPLE .Uranium dioxide U-O2, mass 50 milligram in + cylindrical stainless steel capsule ENDBIB 4 -NOCOMMON +NOCOMMON 0 0 DATA 4 1 DATA ERR-1 ERR-2 ERR-T NO-DIM PER-CENT PER-CENT PER-CENT 0.111 1.8 2.9 3.4 ENDDATA 3 ENDSUBENT 12 -SUBENT 41374007 20000627 20010329 20050926 0000 +SUBENT 41374007 20110624 20111003 20110930 4153 BIB 2 4 REACTION ((92-U-238(N,F),,SIG,,FST)/ (92-U-235(N,F),,SIG,,FST)) -SAMPLE .Uranium Dioxide U-O2, Mass 50 Milligram in - Cylindrical Stainless Steel Capsule +SAMPLE .Uranium dioxide U-O2, mass 50 milligram in + cylindrical stainless steel capsule ENDBIB 4 -NOCOMMON +NOCOMMON 0 0 DATA 4 1 DATA ERR-1 ERR-2 ERR-T NO-DIM PER-CENT PER-CENT PER-CENT 0.0794 4.2 7.2 8.3 ENDDATA 3 ENDSUBENT 12 -SUBENT 41374008 20000627 20010329 20050926 0000 -BIB 2 4 -REACTION ((92-U-238(N,G)92-U-239,,SIG,,FST)/ - (92-U-238(N,F),,SIG,,FST)) -SAMPLE .Uranium Dioxide U-O2, Mass 50 Milligram in - Cylindrical Stainless Steel Capsule -ENDBIB 4 -NOCOMMON +SUBENT 41374008 20110624 20111003 20110930 4153 +BIB 2 3 +REACTION (92-U-238(N,ABS),,ALF,,FST) +SAMPLE .Uranium dioxide U-O2, mass 50 milligram in + cylindrical stainless steel capsule +ENDBIB 3 +NOCOMMON 0 0 DATA 4 1 DATA ERR-1 ERR-2 ERR-T NO-DIM PER-CENT PER-CENT PER-CENT 1.4 3.9 7. 8. ENDDATA 3 -ENDSUBENT 12 -SUBENT 41374009 20000627 20010329 20050926 0000 +ENDSUBENT 11 +SUBENT 41374009 20110624 20111003 20110930 4153 BIB 2 4 REACTION ((92-U-238(N,G)92-U-239,,SIG,,FST)/ (92-U-235(N,G)92-U-236,,SIG,,FST)) -SAMPLE .Uranium Dioxide U-O2, Mass 50 Milligram in - Cylindrical Stainless Steel Capsule +SAMPLE .Uranium dioxide U-O2, mass 50 milligram in + cylindrical stainless steel capsule ENDBIB 4 -NOCOMMON +NOCOMMON 0 0 DATA 4 1 DATA ERR-1 ERR-2 ERR-T NO-DIM PER-CENT PER-CENT PER-CENT diff --git a/exforall/414/41438.x4 b/exforall/414/41438.x4 index fd303ce36..ed4de80f3 100644 --- a/exforall/414/41438.x4 +++ b/exforall/414/41438.x4 @@ -1,31 +1,54 @@ -ENTRY 41438 20050425 20051109 20050811 4134 -SUBENT 41438001 20050425 20051109 20050811 4134 -BIB 9 16 -TITLE Energy Dependence of Related Yield and Period of - Delayed Neutrons Several Groups by Pu-239 Fission in - Primary Neutron Range 0.37-4.97 MeV -AUTHOR (V.M.PIKSAYKIN,L.E.KAZAKOV,S.G.ISAEV,G.G.KOROLEV, - V.A.ROSCHENKO,R.G.TERTYCHNY) +ENTRY 41438 20110623 20111003 20110930 4153 +SUBENT 41438001 20110623 20111003 20110930 4153 +BIB 9 20 +TITLE Energy Dependence of the Relative Yield and Period of + Individual Groups of Delayed Neutrons in Pu-239 Fission + in Primary-Neutron Energy Range 0.37-4.97 MeV +AUTHOR (V.M.Piksaykin,L.E.Kazakov,S.G.Isaev,G.G.Korolev, + V.A.Roschenko,R.G.Tertychnyi) INSTITUTE (4RUSFEI) -REFERENCE (J,AE,92,(3),233,200203) Main Reference -FACILITY (VDG) Cascade Generator Kg-2.5 -METHOD (ACTIV) Radiation Time=15, 180, 300 Seconds. - Activation Mesuring Time= 720 Seconds. +REFERENCE (J,AE,92,(3),233,200203) Main reference + (J,AE/T,92,(3),254,2002) Engl. transl. of J,AE,92 . + #doi:10.1023/A:1016050131272 +FACILITY (VDG) Cascade Generator KG-2.5 +METHOD (ACTIV) Radiation time=15, 180, 300 seconds. + Activation measuring time= 720 seconds. INC-SOURCE (P-T,D-D) -COMMENT Work was Made by Support of Russian Fond of +COMMENT Work was made by support of Russian Fond of Fundamental Investigations in Kaluga Region #00-02-96004 -HISTORY (20041208C) Compiled at the Centre - Cjd +HISTORY (20041208C) Compiled at the Centre - CJD (20050425U) Last checking has been done. -ENDBIB 16 + (20110623U) Engl. translation of J,AE was added. + STATUS and COVARIANCE were added. +ENDBIB 20 NOCOMMON 0 0 -ENDSUBENT 19 -SUBENT 41438002 20050425 20051109 20050811 4134 -BIB 2 3 +ENDSUBENT 23 +SUBENT 41438002 20110623 20111003 20110930 4153 +BIB 4 22 REACTION ((94-PU-239(N,F),DL/GRP,NU)/(94-PU-239(N,F),DL,NU)) - 6-Group Delayed Neutron Abudances -ERR-ANALYS (DATA-ERR) Errors are not Specified -ENDBIB 3 + 6-Group Delayed Neutron Abundances +ERR-ANALYS (DATA-ERR) Errors are not specified +COVARIANCE Correlation matrix: + a1 T1 a2 T2 a3 T3 a4 T4 a5 T5 a6 T6 + a1 1. + T1 0. 1. + a2 0. 0.77 1. + T2 0. -.18 0.09 1. + a3 0. 0.26 0.41 0.33 1. + T3 0. -.13 -.16 0.65 -.22 1. + a4 0. 0.43 0.6 0.45 -.07 0.51 1. + T4 0. 0.08 0.14 0.01 -.46 0. 0.12 1. + a5 0. 0.08 0.11 0.06 0.02 0.03 -.05 0.19 1. + T5 0. 0.04 0.06 0.05 0.01 0.05 -.07 0.09 0. 1. + a6 0. 0.01 0.02 0.01 0. 0. 0. 0.03 -.01 0. 1. + T6 0. 0.01 0.02 0.01 0. 0. 0. 0.04 -.01 0. 0. 1. + ai - relative yield, + Ti - HL of delayed neutrons. +STATUS (TABLE) Table 1 of J,AE,92. + (COREL,41415002) In 41415 - 8-group delayed neutron + abundances. +ENDBIB 22 NOCOMMON 0 0 DATA 6 54 EN EN-ERR HL HL-ERR DATA DATA-ERR @@ -85,5 +108,5 @@ MEV MEV SEC SEC NO-DIM NO-DIM 4.97 0.13 0.553 0.019 0.109 0.004 4.97 0.13 0.217 0.008 0.036 0.001 ENDDATA 56 -ENDSUBENT 64 +ENDSUBENT 83 ENDENTRY 2 diff --git a/exforall/414/41439.x4 b/exforall/414/41439.x4 index b1223507a..8bdfe7fb5 100644 --- a/exforall/414/41439.x4 +++ b/exforall/414/41439.x4 @@ -1,34 +1,74 @@ -ENTRY 41439 20050425 20051109 20050811 4134 -SUBENT 41439001 20050425 20051109 20050811 4134 -BIB 10 18 -TITLE Related Yield and Period of Several Groups For - Delayed Neutrons from Epithermal Neutron Fission of - U-233, U-235 and Pu-239 -AUTHOR (V.M.PIKSAYKIN,L.E.KAZAKOV,G.G.KOROLEV,S.G.ISAEV, - V.A.ROSCHENKO,M.Z.TARASKO) +ENTRY 41439 20110623 20111003 20110930 4153 +SUBENT 41439001 20110623 20111003 20110930 4153 +BIB 10 23 +TITLE Relative Yield and Period of Individual Groups of + Delayed Neutrons in U-233, U-235, and Pu-239 Fission by + Epithermal Neutrons . +AUTHOR (V.M.Piksaykin,L.E.Kazakov,G.G.Korolev,S.G.Isaev, + V.A.Roschenko,M.Z.Tarasko) INSTITUTE (4RUSFEI) -REFERENCE (J,AE,92,(2),135,200202) Main Reference -FACILITY (VDG) Cascade Generator Kg-2.5 -METHOD (ACTIV) Radiation Time=15, 180, 300 Seconds. - Registration Time of Delayed Neutron Intensity 724.5 S -DETECTOR (D4PI) Distributed in Polyethilene Cube Along - Three Concentric Circles Assemblage of 30 Boron - Counters Snm-11 was Used For Neutron Detection +REFERENCE (J,AE,92,(2),135,200202) Main reference + (J,AE/T,92,(2),147,2002) Engl. transl. of J,AE,92. + #doi:10.1023/A:1015878706836 +FACILITY (VDG) Cascade Generator KG-2.5 +METHOD (ACTIV) Radiation time=15, 180, 300 seconds. + Registration time of delayed neutron intensity 724.5 s +DETECTOR (D4PI) Distributed in polyethylene cube along + three concentric circles assemblage of 30 boron + counters SNM-11 was used for neutron detection INC-SOURCE (P-T) -INC-SPECT Epithermal Neutron Spectrum Averaged Over Sample Volume - Is Presented in Fig.2 of Reference -HISTORY (20041227C) Compiled at the Centre - Cjd +INC-SPECT Epithermal neutron spectrum averaged over sample volume + is presented in Fig.2 of J,AE,92,(2),135,2002. +HISTORY (20041227C) Compiled at the Centre - CJD (20050425U) Last checking has been done. -ENDBIB 18 + (20110623U) Engl. translation of J,AE was added. + TABLE was added in STATUS. + COVARIANCEs were added. +ENDBIB 23 NOCOMMON 0 0 -ENDSUBENT 21 -SUBENT 41439002 20050425 20051109 20050811 4134 -BIB 3 4 +ENDSUBENT 26 +SUBENT 41439002 20110623 20111003 20110930 4153 +BIB 4 39 REACTION ((94-PU-239(N,F),DL/GRP,NU)/(94-PU-239(N,F),DL,NU)) 6-Group Delayed Neutron Abundances -ERR-ANALYS (DATA-ERR) Errors are not Specified -STATUS Data from Table 1 -ENDBIB 4 +ERR-ANALYS (DATA-ERR) Errors are not specified +COVARIANCE Correlation matrix: + a1 T1 a2 T2 a3 T3 a4 T4 a5 T5 a6 T6 + a1 1. + T1 0. 1. + a2 0. 0.82 1. + T2 0. -.05 0.19 1. + a3 0. 0.32 0.46 0.34 1. + T3 0. -.09 -.11 0.65 -.27 1. + a4 0. 0.5 0.64 0.50 -.03 0.54 1. + T4 0. 0.06 0.11 0. -.53 0.09 0.17 1. + a5 0. 0.09 0.12 0.06 0.01 0.03 -.04 0.21 1. + T5 0. 0.04 0.05 0.05 0.01 0.05 -.07 0.08 0.01 1. + a6 0. 0.02 0.03 0.01 0. 0. 0. 0.05 -.02 .01 1 + T6 0. 0.03 0.03 0.02 0. 0.01 -.01 0.06 -.02 0. 0 1. + Covariation matrix: + a1 T1 a2 T2 a3 T3 a4 T4 + a1 6.3-7 + T1 0. 2.2 + a2 0. 2.6-3 4.7-5 + T2 0. -2.6-3 1.4-4 1.1-2 + a3 0. 8.0-4 1.7-5 2.0-4 2.9-5 + T3 0. -3.6-3 -6.1-5 5.8-3 -1.2-4 7.0-3 + a4 0. 1.5-3 2.8-5 3.3-4 -8.7-7 2.8-4 3.9-5 + T4 0. 1.2-3 2.9-5 -1.5-5 -1.2-4 2.9-4 4.2-5 1.6-3 + a5 0. 1.2-4 2.3-6 2.0-5 1.5-7 7.0-6 -7.3-7 2.5-5 + T5 0. 3.9-4 7.3-6 1.1-4 1.2-6 9.3-5 -9.4-6 7.0-5 + a6 0. 1.5-5 3.2-7 2.2-6 -2.5-9 -1.2-7 -5.4-9 3.1-6 + T6 0. 1.1-4 1.9-6 1.8-5 -4.2-9 7.0-6 -5.8-7 2.2-5 + a5 T5 a6 T6 + a5 8.3-6 + T5 6.4-7 4.7-4 + a6 -8.9-8 3.4-7 2.3-6 + T6 -3.9-7 2.2-8 -1.4-9 8.1-5 + ai - relative yield, + Ti - HL of delayed neutrons precursors. +STATUS (TABLE) Data from Table 1 of J,AE,92,(2),135,2002. +ENDBIB 39 COMMON 1 3 EN-DUMMY EV @@ -44,14 +84,49 @@ SEC SEC NO-DIM NO-DIM 0.621 0.022 0.084 0.003 0.256 0.009 0.043 0.002 ENDDATA 8 -ENDSUBENT 21 -SUBENT 41439003 20050425 20051109 20050811 4134 -BIB 3 4 +ENDSUBENT 56 +SUBENT 41439003 20110623 20111003 20110930 4153 +BIB 4 39 REACTION ((92-U-233(N,F),DL/GRP,NU)/(92-U-233(N,F),DL,NU)) 6-Group Delayed Neutron Abundances ERR-ANALYS (DATA-ERR) Errors are not Specified -STATUS Data from Table 1 -ENDBIB 4 +COVARIANCE Correlation matrix: + a1 T1 a2 T2 a3 T3 a4 T4 a5 T5 a6 T6 + a1 1. + T1 0. 1. + a2 0. 0.85 1. + T2 0. 0.65 0.35 1. + a3 0. 0.5 0.39 0.52 1. + T3 0. 0.21 -.8 0.62 -.10 1. + a4 0. 0.51 0.33 0.56 -.22 0.65 1. + T4 0. 0.04 0.11 -.02 -.50 -.05 0.16 1. + a5 0. 0.05 0.04 0.05 -.01 0.03 -.05 0.12 1. + T5 0. 0.03 0.02 0.04 0. 0.04 -.05 0.05 0. 1. + a6 0. 0.02 0.02 0.01 0. 0.01 -.01 0.05 -.01 0. 1 + T6 0. 0.02 0.01 0.02 0. 0.01 -.02 0.05 -.01 0. 0. 1. + Covariation matrix: + a1 T1 a2 T2 a3 T3 a4 T4 + a1 1.1-6 + T1 0. 3.9-2 + a2 0. 6.0-4 1.3-5 + T2 0. 1.6-2 1.6-4 1.6-2 + a3 0. 3.6-4 5.1-6 2.4-4 1.4-5 + T3 0. 2.1-3 -3.3-5 4.1-3 -1.9-5 2.7-3 + a4 0. 2.9-4 3.4-6 2.0-4 -2.3-6 9.5-5 8.1-6 + T4 0. 1.9-4 9.7-6 -7.4-5 -4.6-5 -6.4-5 1.2-5 6.5-4 + a5 0. 1.1-5 1.6-7 6.9-6 -2.5-8 1.7-6 -1.5-7 3.2-6 + T5 0. 7.8-5 9.7-7 6.6-5 -2.3-7 2.7-5 -1.9-6 1.5-5 + a6 0. 2.8-6 3.9-8 1.2-6 -1.2-8 5.2-7 -1.1-8 9.0-7 + T6 0. 2.4-5 2.2-7 1.5-5 -3.8-8 3.5-6 -2.9-7 7.0-6 + a5 T5 a6 T6 + a5 1.2-6 + T5 -1.2-9 1.7-4 + a6 -7.9-9 .92-9 5.2-7 + T6 -6.4-8 -3.6-9 -1.2-9 3.4-5 + ai - relative yield, + Ti - HL of delayed neutrons. +STATUS (TABLE) Data from Table 1 of J,AE,92,(2),135,2002. +ENDBIB 39 COMMON 1 3 EN-DUMMY EV @@ -67,14 +142,51 @@ SEC SEC NO-DIM NO-DIM 0.611 0.013 0.051 0.001 0.276 0.006 0.034 0.001 ENDDATA 8 -ENDSUBENT 21 -SUBENT 41439004 20050425 20051109 20050811 4134 -BIB 3 4 +ENDSUBENT 56 +SUBENT 41439004 20110623 20111003 20110930 4153 +BIB 4 41 REACTION ((92-U-235(N,F),DL/GRP,NU)/(92-U-235(N,F),DL,NU)) 6-Group Delayed Neutron Abundances ERR-ANALYS (DATA-ERR) Errors are not Specified -STATUS Data from Table 1 -ENDBIB 4 +COVARIANCE Correlation matrix: + a1 T1 a2 T2 a3 T3 a4 T4 a5 T5 a6 T6 + a1 1. + T1 0. 1. + a2 0. 0.86 1. + T2 0. 0.43 0.24 1. + a3 0. 0.37 0.41 0.26 1. + T3 0. 0.16 -.14 0.68 -.38 1. + a4 0. 0.67 0.55 0.68 -.07 0.65 1. + T4 0. 0.13 0.1 0.18 -.59 0.36 0.24 1. + a5 0. 0.13 0.13 0.11 -.02 0.06 -.02 0.3 1. + T5 0. 0.09 0.08 0.08 0.01 0.05 -.10 0.22 -.01 1. + a6 0. 0.02 0.01 0.02 0.01 0. 0.01 0.01 -.01 0. 1 + T6 0. 0.01 0.01 0.01 0. 0. 0. 0.03 -.02 0. 0. 1. + Covariation matrix: + a1 T1 a2 T2 a3 T3 a4 T4 + a1 5.1-7 + T1 0. 8.1-2 + a2 0. 9.5-4 1.5-3 + T2 0. 1.6-2 1.2-4 1.7-2 + a3 0. 4.6-4 6.9-6 1.5-4 1.9-5 + T3 0. 3.7-3 -4.4-5 7.5-3 -1.4-4 6.9-3 + a4 0. 9.8-4 1.1-5 4.6-4 -1.5-6 2.8-4 2.7-5 + T4 0. 1.2-3 1.2-5 7.8-4 -8.5-5 9.7-4 4.1-5 1.1-3 + a5 0. 1.6-4 2.1-6 6.4-5 -3.2-7 2.1-5 -3.7-7 4.2-5 + T5 0. 4.1-4 5.0-6 1.8-4 4.1-7 7.2-5 -8.5-6 1.2-4 + a6 0. 4.2-6 5.2-8 2.4-6 2.4-8 3.0-7 5.9-8 4.4-7 + T6 0. 2.2-5 3.0-7 7.4-6 -3.6-8 2.0-6 2.5-8 6.1-6 + a5 T5 a6 T6 + a5 1.8-5 + T5 -7.8-7 2.9-4 + a6 -3.9-8 -9.2-9 8.3-7 + T6 -4.2-7 -4.2-9 1.5-9 4.0-5 + ai - relative yield, + Ti - HL of delayed neutrons. +STATUS (TABLE) Data from Table 1 of J,AE,92,(2),135,2002. + (COREL,41419003) In 41419 - 8-group delayed neutron + abundances . +ENDBIB 41 COMMON 1 3 EN-DUMMY EV @@ -90,5 +202,5 @@ SEC SEC NO-DIM NO-DIM 0.494 0.017 0.132 0.004 0.179 0.006 0.026 0.001 ENDDATA 8 -ENDSUBENT 21 +ENDSUBENT 58 ENDENTRY 4 diff --git a/exforall/414/41460.x4 b/exforall/414/41460.x4 index f42f59b45..0f9efee74 100644 --- a/exforall/414/41460.x4 +++ b/exforall/414/41460.x4 @@ -1,26 +1,30 @@ -ENTRY 41460 20060120 20060525 20060324 4137 -SUBENT 41460001 20060120 20060525 20060324 4137 -BIB 10 13 +ENTRY 41460 20110726 20111003 20110930 4153 +SUBENT 41460001 20110726 20111003 20110930 4153 +BIB 10 17 TITLE Double-quantum Cascades After Thermal Neutron Capture In 149-Sm Nucleus -AUTHOR (E.V.VASIL'EVA,A.V.VOYNOV,O.D.KYOSTAROVA,V.D.KULIK, - A.M.SUKHOVOY,V.A.KHITROV,YU.V.KHOL'NOV,V.H.SHILIN) +AUTHOR (E.V.Vasil'eva,A.V.Voynov,O.D.Kyostarova,V.D.Kulik, + A.M.Sukhovoy,V.A.Khitrov,Yu.V.Khol'Nov,V.H.Shilin) INSTITUTE (4ZZZDUB) -REFERENCE (J,IZV,57,(9),128,199309) -FACILITY (REAC,4ZZZDUB) IBR-30 Of Neutron Physics Laboratory +REFERENCE (J,IZV,57,(9),128,199309) Data tables. + (J,BAS,57,(9),1591,1993) Engl.translation of J,IZV,57. + (R,JINR-P6-2,199301) Previous publication. +FACILITY (REAC,4ZZZDUB) IBR-30 of Neutron Physics Laboratory SAMPLE Natural samarium isotopes composition DETECTOR (NAICR) Two NaI(Tl) detectors (GELI) Two Ge(Li) detectors INC-SOURCE (REAC) Thermal neutrons -INC-SPECT Termal neutrons of reactor IBR-30 +INC-SPECT Thermal neutrons of reactor IBR-30 HISTORY (20060120C) Compiled at CJD (M.M.) -ENDBIB 13 + (20110726A) M.M. Refs. R,JINR-P6-2,1993; J,BAS,57 + were added. +ENDBIB 17 COMMON 1 3 EN-DUMMY EV 0.0253 ENDCOMMON 3 -ENDSUBENT 20 +ENDSUBENT 24 SUBENT 41460002 20060120 20060525 20060324 4137 BIB 5 6 REACTION (62-SM-149(N,2G)62-SM-150,,SPC,,SPA) Intensity of diff --git a/exforall/414/41487.x4 b/exforall/414/41487.x4 index dc404f959..f3e983b25 100644 --- a/exforall/414/41487.x4 +++ b/exforall/414/41487.x4 @@ -1,6 +1,6 @@ -ENTRY 41487 20110320 20110624 20110623 4152 -SUBENT 41487001 20110320 20110624 20110623 4152 -BIB 15 81 +ENTRY 41487 20110812 20111003 20110930 4153 +SUBENT 41487001 20110812 20111003 20110930 4153 +BIB 15 84 REFERENCE (C,2007SANIB,,462,200710) Main ref. (C,2004SANTA,1,865,2004) Graphs. (J,NP/A,734,(1),E45,2004) Preliminary Results as Graphs @@ -74,17 +74,20 @@ HISTORY (20070214C) Compiled at CJD (M.M.) The 0. value of error (5) in Tables 1, 2 of C,2007SANIB,,462,2007 was corrected according to the comment of A.Laptev - alaptev@lanl.gov . - Comment was added in Subnets 002-003 according to + Comment was added in Subents 002-003 according to N.Otsuka's opinion. + (20110812A) M.M. In Subents 014,015: + ENDF-B/VII.0 -> ENDF/B-VII.0 + according to the comment of M.Bossant. STATUS (APRVD) Data received from author O.Shcherbakov,2007 . from A.Laptev via S.Hlavac, 2008 , from A.Laptev via N.Otsuka, 6.03.2011. Approved by O.Shcherbakov 30.03.2011. (COREL,41444001) Experiment is the same, normalization differs. -ENDBIB 81 +ENDBIB 84 NOCOMMON 0 0 -ENDSUBENT 84 +ENDSUBENT 87 SUBENT 41487002 20110320 20110624 20110623 4152 BIB 5 25 REACTION ((94-PU-240(N,F),,SIG)/(92-U-235(N,F),,SIG)) @@ -2382,7 +2385,7 @@ MEV PER-CENT MB MB PER-CENT PER-CENT 216.1 1. 1.560 0.117 0.4 3.5 ENDDATA 16 ENDSUBENT 56 -SUBENT 41487014 20110320 20110624 20110623 4152 +SUBENT 41487014 20110812 20111003 20110930 4153 BIB 7 24 REACTION ((94-PU-240(N,F),,SIG)/(92-U-235(N,F),,SIG)) SAMPLE Isotopic composition (weight %) : @@ -2391,7 +2394,7 @@ SAMPLE Isotopic composition (weight %) : MONITOR ((94-PU-240(N,F),,SIG)/(92-U-235(N,F),,SIG)) at 1, 5 and 10 MeV MONIT-REF (,V.Pronyaev+,R,STI/PUB-129,122,2007) 235U(n,f) - (,L.W.Weston+,3,ENDF-B/VII.0,9440,2006) 240Pu(n,f) + (,L.W.Weston+,3,ENDF/B-VII.0,9440,2006) 240Pu(n,f) ERR-ANALYS (ERR-S) Statistical Error Estimated systematic uncertainty caused by (ERR-1)- separation of fission and background events in @@ -2753,13 +2756,13 @@ PER-CENT PER-CENT 0.5 ENDDATA 336 ENDSUBENT 369 -SUBENT 41487015 20110320 20110624 20110623 4152 +SUBENT 41487015 20110812 20111003 20110930 4153 BIB 6 21 REACTION ((95-AM-243(N,F),,SIG)/(92-U-235(N,F),,SIG)) MONITOR ((95-AM-243(N,F),,SIG)/(92-U-235(N,F),,SIG)) at 1, 5 and 10 MeV MONIT-REF (,V.Pronyaev+,R,STI/PUB-129,122,2007) 235U(n,f) - (,P.G.Young+,3,ENDF-B/VII.0,9549,2006) 243Am(n,f) + (,P.G.Young+,3,ENDF/B-VII.0,9549,2006) 243Am(n,f) ERR-ANALYS (ERR-S) Statistical Error Estimated systematic uncertainty caused by (ERR-1)- separation of fission and background events in diff --git a/exforall/415/41508.x4 b/exforall/415/41508.x4 index cf665ce61..5f13ad5e3 100644 --- a/exforall/415/41508.x4 +++ b/exforall/415/41508.x4 @@ -1,12 +1,14 @@ -ENTRY 41508 20080511 20080801 20080721 4143 -SUBENT 41508001 20080511 20080801 20080721 4143 -BIB 14 27 -TITLE Relative yield of delayed neutrons and half-lives of - their precursors at neutron induced fission of Pu-239 - in the incident neutron energy range 14.2 - 17.9 MeV. +ENTRY 41508 20110623 20111003 20110930 4153 +SUBENT 41508001 20110623 20111003 20110930 4153 +BIB 14 30 +TITLE Relative yield of delayed neutrons and half-life of + their precursor nuclei with fissioning of Pu-239 by + 14.2-17.9 MeV neutrons . AUTHOR (V.A.Roschenko, V.M.Piksaykin, L.E.Kazakov,G.G.Korolev) INSTITUTE (4RUSFEI) REFERENCE (J,AE,101,(6),441,200612) Main Reference + (J,AE/T,101,(6),897,2006) Engl. transl. of J,AE,101 . + #doi:10.1007/s10512-006-0188-z REL-REF (N,,V.M.Piksaikin+,J,PNE,41,(1-4),203,2002) (N,,V.M.Piksaikin+,J,AE,85,(1),51,1998) Experiment details. @@ -28,11 +30,12 @@ COMMENT Work was Made by Support of Russian Fond of Bound Researches and Administration of Kaluga Region #05-02-08044. HISTORY (20080411C) Compiled at CJD. M.M. -ENDBIB 27 + (20110623U) Engl. translation of J,AE was added. +ENDBIB 30 NOCOMMON 0 0 -ENDSUBENT 30 -SUBENT 41508002 20080411 20080801 20080721 4143 -BIB 3 19 +ENDSUBENT 33 +SUBENT 41508002 20110623 20111003 20110930 4153 +BIB 4 20 REACTION ((94-PU-239(N,F),DL/GRP,NU)/(94-PU-239(N,F),DL,NU)) 6-Group Delayed Neutron Abundances ERR-ANALYS (DATA-ERR) Errors are not specified @@ -52,7 +55,8 @@ COVARIANCE Correlation matrix: T5 0. 0.04 0.06 0.05 0.01 0.05 -.07 0.09 0. 1 a6 0. 0.01 0.02 0.01 0. 0. 0. 0.03 -.01 0 1 T6 0. 0.01 0.02 0.01 0. 0. 0. 0.04 -.01 0 0 1 -ENDBIB 19 +STATUS (TABLE) Table 1 of J,AE,101,(6),441,2006. +ENDBIB 20 COMMON 1 3 EN-RSL MEV @@ -80,5 +84,5 @@ MEV SEC SEC NO-DIM NO-DIM 17.9 0.53 0.02 0.124 0.004 17.9 0.217 0.006 0.040 0.001 ENDDATA 20 -ENDSUBENT 48 +ENDSUBENT 49 ENDENTRY 2 diff --git a/exforall/415/41551.x4 b/exforall/415/41551.x4 new file mode 100644 index 000000000..2294c3e5d --- /dev/null +++ b/exforall/415/41551.x4 @@ -0,0 +1,67 @@ +ENTRY 41551 20110624 20111003 20110930 4153 +SUBENT 41551001 20110624 20111003 20110930 4153 +BIB 10 33 +TITLE Measuring of high energy gamma-ray emission + accompanying the spontaneous fission of the Cf-252 + nuclei . +AUTHOR (N.V.Eremin,S.S.Markochev,A.A.Paskhalov,E.A.Tsvetkov, + G.Mandaglio, M.Manganaro, G.Fazio, G.Giargina, + M.V.Romaniuk) +INSTITUTE (4RUSMOS) N.V.Eremin, A.A.Paskhalov + (4RUSMFT) S.S.Markochev, E.A.Tsvetkov + (2ITYSIC) G.Mandaglio, M.Manganaro,G.Fazio, G.Giargina + (2ITYMES) G.Mandaglio, M.Manganaro,G.Fazio, G.Giargina, + M.V.Romaniuk + (4UKRIJD) M.V.Romaniuk +REFERENCE (J,IZV,75,(4),580,2011) Main Reference + (J,BAS,75,(4),544,2011) Engl. transl. of J,IZV + #doi:10.3103/S1062873811040113 + (J,IMP/E,19,(5-6),1183,2010) Previous publication . +PART-DET (N,G) +METHOD (COINC) Gammas-neutrons and gamma-gamma coincidence in + (TOF) combination with time-of-flight method. + Time of coincidence measurement - 500 hr. +DETECTOR (SCIN,BGO) Two scintillators : + - BGO crystal of 7.6 cm diameter, 7.6 cm long, + registration threshold 5 MeV - for gammas; + - polistirol 6.0cm diameter, 2.0 cm long- for neutrons + Standard sources Cs-137, Co-60, Pu(Be) were used for + calibration of BGO-detector. Gamma registration + efficiency was calculated by code GEANT4 to be about + 35 % at 60 MeV. +SAMPLE Cf-252 source of 6.1E+6 n/sec activity. + 10 cm distance between BGO-detector and Cf source. +CORRECTION For gamma-gamma and random coincidences. + For background. +HISTORY (20110624C) Compiled at CJD. M.M. +ENDBIB 33 +NOCOMMON 0 0 +ENDSUBENT 36 +SUBENT 41551002 20110624 20111003 20110930 4153 +BIB 5 16 +REACTION (98-CF-252(0,F)0-G-0,,MLT/DE,,MSC) + Photon emission in spontaneous fission. +REL-REF (A,,J.Kasagi+,J,JPJ/S,58,620,1989) + (A,,Yu.N.Pokotilovskiy,J,YF,52,942,1990) + (A,,S.J.Luke+,J,PR/C,44,1548,1991) + (A,,H.Van der Ploeg+,J,PRL,68,3145,1992) + (A,,V.A.Varlachev+,J,ZEP,82,440,2005) + Agree in energy range < 20 MeV. +ERR-ANALYS (DATA-ERR) Errors are not specified +STATUS (TABLE) Text, page 582 of J,IZV,75,(4),580,2011; + also data are on Fig.3 of J,IZV,75,(4),580,2011 = + Fig.2 of J,IMP/E,19,(5-6),1183,2010. + Request for the data of Fig.3 was sent 24.06.2011 to + Sergey Markochev: sergey.markochev@gmail.com +HISTORY (20110928A) M.M. MSC in REACTION was added according to + the comment of N.Otsuka (NDS, IAEA). +ENDBIB 16 +NOCOMMON 0 0 +DATA 2 2 +E DATA +MEV PT/FIS/MEV + 20. 1.E-7 + 60. 1.E-8 +ENDDATA 4 +ENDSUBENT 25 +ENDENTRY 2 diff --git a/exforall/415/41563.x4 b/exforall/415/41563.x4 index 23fea8d07..5fe82b716 100644 --- a/exforall/415/41563.x4 +++ b/exforall/415/41563.x4 @@ -1,19 +1,19 @@ -ENTRY 41563 20110401 20110624 20110623 4152 -SUBENT 41563001 20110401 20110624 20110623 4152 -BIB 15 29 +ENTRY 41563 20110812 20111003 20110930 4153 +SUBENT 41563001 20110812 20111003 20110930 4153 +BIB 15 32 TITLE Isomeric yield ratios of the (gamma,n) and (n,2n) - reactions nuclei of Pd-110, Nd-142d and Sm-144. + reactions nuclei of Pd-110, Nd-142 and Sm-144. AUTHOR (S.R.Palvanov,Zh.Rakhmonov,M.Kayumov, M.I.Mamayusupova, O.Zhuraev) REFERENCE (J,IZV,75,(2),239,2011) Main ref. (J,BAS,75,(2),222,2011) Engl. translation of J,BAS,75 . #doi:10.3103/S1062873811020262 REL-REF (R,,C.Lederer,B,LEDERER-7,,1978) Decay data. -INSTITUTE (4UZ UZ) Research Institute of Applied Physics, +INSTITUTE (4UZ UZB) Zh.Rakhmonov,M.Kayumov, O.Zhuraev . + (4UZ UZ) Research Institute of Applied Physics, National University of Uzbekistan, Tashkent. - S.R.Palvanov, M.I.Mamayusupova - (4UZ UZB) Zh.Rakhmonov,M.Kayumov, O.Zhuraev . -FACILITY (ACCEL,4UZ UZ) NG-150 neutron generator. +FACILITY (NGEN,4UZ UZB) NG-150 neutron generator. INC-SOURCE (D-D) Deuterium target. (D-T) Tritium target. INC-SPECT Neutron fluxes about 10**8 and 10**10 n/sec. @@ -30,14 +30,17 @@ ERR-ANALYS (DATA-ERR) Absolute error was determined by: and efficiency of detection. STATUS (COREL,M0812001) Data for gamma-induced reactions. HISTORY (20110401C) M.M. Compiled at CJD. -ENDBIB 29 + (20110812A) M.M. In Subent 002 REL-REF: + J,PR,1 -> J,PR/C,1 + according to the comment of M.Bossant. +ENDBIB 32 COMMON 1 3 EN MEV 14. ENDCOMMON 3 -ENDSUBENT 36 -SUBENT 41563002 20110401 20110624 20110623 4152 +ENDSUBENT 39 +SUBENT 41563002 20110812 20111003 20110930 4153 BIB 5 10 REACTION (46-PD-110(N,2N)46-PD-109-M/G,,SIG/RAT) DECAY-DATA (46-PD-109-M,4.69MIN,DG,188.9,.5800) @@ -45,7 +48,7 @@ DECAY-DATA (46-PD-109-M,4.69MIN,DG,188.9,.5800) (46-PD-109-G,13.47HR,DG,88.10,.0500) REL-REF (A,,Hoang Dac Luc+,J,BJP,14,(2),152,1987) (A,,S.L.Sothrass,T,SOTHRASS,1977) - (A,,Wen-Deh Lu+,J,PR,1,350,1970) + (A,,Wen-Deh Lu+,J,PR/C,1,350,1970) CRITIQUE In the Table 1 product nuclei Pd-109m,g by mistake are presented as Pd-95m,g. STATUS (TABLE) Table 3 of J,IZV,75,(2),239,2011. @@ -57,9 +60,9 @@ NO-DIM NO-DIM 0.42 0.03 ENDDATA 3 ENDSUBENT 18 -SUBENT 41563003 20110401 20110624 20110623 4152 +SUBENT 41563003 20110812 20111003 20110930 4153 BIB 4 15 -REACTION (60-ND-142(G,N)60-ND-141-M/G,,SIG/RAT,,BRA) +REACTION (60-ND-142(N,2N)60-ND-141-M/G,,SIG/RAT) DECAY-DATA (60-ND-141-M,60.3SEC,DG,756.5,.91) Branching coefficient 0.9997 (60-ND-141-G,2.6HR,DG,91.10,.2830, @@ -82,9 +85,9 @@ NO-DIM NO-DIM 0.47 0.04 ENDDATA 3 ENDSUBENT 23 -SUBENT 41563004 20110401 20110624 20110623 4152 +SUBENT 41563004 20110812 20111003 20110930 4153 BIB 5 15 -REACTION (62-SM-144(G,N)62-SM-143-M/G,,SIG/RAT,,BRA) +REACTION (62-SM-144(N,2N)62-SM-143-M/G,,SIG/RAT) DECAY-DATA (62-SM-143-M,65.SEC,DG,690.00,.0167, DG,754.4,1.00, DG,963.00,0.0113) diff --git a/exforall/415/41574.x4 b/exforall/415/41574.x4 new file mode 100644 index 000000000..f3d9699b8 --- /dev/null +++ b/exforall/415/41574.x4 @@ -0,0 +1,80 @@ +ENTRY 41574 20110715 20111003 20110930 4153 +SUBENT 41574001 20110715 20111003 20110930 4153 +BIB 14 26 +TITLE Using a linear polarimeter for investigating the + gamma-radiation of an (n, n'gamma) reaction. +AUTHOR (L.I.Govor, A.M.Demidov, O.K.Zhuravlev, V.A.Kurkin, + Yu.K.Cherepantsev) +REFERENCE (J,AE,57,(4),270,198410) + (J,SJA,57,(4),732,1984) + #doi:10.1007/BF01123648 +INSTITUTE (4RUSKUR) IR-8 reactor +INC-SOURCE (REAC) Horizontal channel. Filter of Cd layer of 1 mm + thickness, B4C layer of 10 mm thickness, U layer of + 50 mm thickness. +REL-REF (M,,Demidov+,J,IZV,44,(1),135,198001) + Description of incident spectrum and detector +FACILITY (REAC,4RUSKUR) IR-8 reactor . +INC-SPECT Neutron beam was passed through a filter of B4-C,Cd, + and lead. At .5MeV neutron spectrum falls off + according to the exp(-0.72E(n))-law approximately. + (Nucl.Instr.and Meth.117(1974)533) +DETECTOR (SPEC,GE) Two Ge detectors of 40 mm diameter, 40 mm + long. Resolution2.3 keV at gamma energy 1.6 MeV. +SAMPLE (60-ND-148,ENR=0.916) 20 g of Nd, size 4x5 cm, + 91.6% enrichment. +METHOD (GSPEC) +PART-DET (G) +ERR-ANALYS (DATA-ERR) Not specified. +HISTORY (20110715C) M.M. +ENDBIB 26 +COMMON 1 3 +EN-DUMMY +MEV + 1. +ENDCOMMON 3 +ENDSUBENT 33 +SUBENT 41574002 20110715 20111003 20110930 4153 +BIB 2 3 +REACTION (60-ND-148(N,INL)60-ND-148,PAR,DA,G,LEG/RS) +STATUS (TABLE) Table 1 of J,AE,57,(4),270,1984 + (COREL,30672006) In 30672 - measurement in 3IRQNRI. +ENDBIB 3 +NOCOMMON 0 0 +DATA 4 10 +E NUMBER DATA DATA-ERR +KEV NO-DIM NO-DIM NO-DIM + 489.96 2. -0.20 0.04 + 489.96 4. 0.04 0.05 + 869.23 2. 0.01 0.04 + 869.23 4. 0.02 0.05 + 947.09 2. -0.06 0.04 + 947.09 4. 0.01 0.04 +1209.92 2. 0.05 0.05 +1209.92 4. 0.06 0.06 +1427.4 2. 0.20 0.05 +1427.4 4. 0.02 0.06 +ENDDATA 12 +ENDSUBENT 20 +SUBENT 41574003 20110715 20111003 20110930 4153 +BIB 3 7 +REACTION (60-ND-148(N,INL)60-ND-148,PAR,POL,G,MSC) + Gamma-ray linear polarization. +ANALYSIS Linear polarization P was determined by N = ratio of + counts measured at 90 degrees to 0 degrees by + polarimeter and R = sensitivity of polarimeter, + using relation P=(1-N*R)/(N-R). +STATUS (TABLE) Table 1 of J,AE,57,(4),270,1984 +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 5 +E DATA DATA-ERR +KEV NO-DIM NO-DIM + 489.96 2.35 0.19 + 869.23 0.75 0.07 + 947.09 0.95 0.14 +1209.92 1.71 0.38 +1427.4 0.57 0.33 +ENDDATA 7 +ENDSUBENT 19 +ENDENTRY 3 diff --git a/exforall/M00/M0036.x4 b/exforall/M00/M0036.x4 index e8a078482..7adca6e72 100644 --- a/exforall/M00/M0036.x4 +++ b/exforall/M00/M0036.x4 @@ -1,80 +1,86 @@ -ENTRY M0036 910204 20050926 0000 -SUBENT M0036001 910204 20050926 0000 -BIB 12 17 -TITLE INVESTIGATION OF THE YIELDS AND ANGULAR DISTRIBUTIONS - OF PHOTONEUTRONS FROM LEAD THICK TARGETS. -AUTHOR (A.P.ANTIPENKO,V.G.BATIY,B.YA.GOLOVNYA,V.I.KASILOV, - N.I.LAPIN,L.A.MAKHNENKO,S.F.SHCHERBAK) -INSTITUTE (4CCPKFT) -REFERENCE (J,AE,48,115,80) -FACILITY (LINAC,4CCPKFT) +ENTRY M0036 20110530 20111003 20110921 M059 +SUBENT M0036001 20110530 20111003 20110921 M059 +BIB 12 22 +TITLE Investigation of the yields and angular distributions + of photoneutrons from lead thick targets. +AUTHOR (A.P.Antipenko,V.G.Batiy,B.Ya.Golovnya,V.I.Kasilov, + N.I.Lapin,L.A.Makhnenko,S.F.Shcherbak) +INSTITUTE (4UKRKFT) +REFERENCE (J,AE,48,115,1980) + (J,SJA,48,139,1980) + English translation of AE,48,115,1980. +FACILITY (LINAC,4UKRKFT) INC-SOURCE (BRST) METHOD (ACTIV) DETECTOR (SCIN) -COMMENT THE YIELDS AND ANGULAR DISTRIBUTIONS OF PHOTONEUTRONS - FROM LEAD TARGETS HAVE BEEN MEASURED IN THE INCIDENT - ELECTRON ENERGY REGION 60 TO 300 MEV. +COMMENT The yields and angular distributions of photoneutrons + from lead targets have been measured in the incident + electron energy region 60 to 300 MeV. ERR-ANALYS NO INFORMATION STATUS (CURVE) -HISTORY (820223C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 17 +HISTORY (19820223C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110530A) Corrected by V.Varlamov: REFERENCE, + INSTITUTE, FACILITY, dates, BRS -> BRA, MISC-COL in + SUBENTs 002, 008, INC-SPEC in SUBENT 007, lowercase. +ENDBIB 22 NOCOMMON 0 0 -ENDSUBENT 20 -SUBENT M0036002 910205 20050926 0000 -BIB 1 3 -REACTION (82-PB-0(G,N),,TTY/DA,,BRS/REL,EXP) - THE SAMPLE THICKNESS ON THIS SUBJECT IS MEASURED AND - GIVEN IN RADIATIVE LENGTHS. -ENDBIB 3 +ENDSUBENT 25 +SUBENT M0036002 20110530 20111003 20110921 M059 +BIB 2 4 +REACTION (82-PB-0(G,X)0-NN-1,,TTY/DA,,BRA/REL) + Neutron flux density in neutron/sec cm**2. +MISC-COL (MISC) The sample thickness on this subject was + measured and given in radiative lengths (= 5.6 mm). +ENDBIB 4 COMMON 1 3 EN-MAX MEV 200. ENDCOMMON 3 DATA 3 33 -ANG THICKNESS DATA -ADEG ARB-UNITS ARB-UNITS - 30. 0.9200 6.3700 - 30. 1.4300 10.3500 - 30. 1.9400 15.5200 - 30. 2.4500 17.7700 - 30. 2.9300 20.8700 - 30. 3.4300 22.1100 - 30. 3.9500 23.5700 - 30. 7.9800 20.5100 - 30. 16.0500 21.1200 - 30. 18.1100 22.4300 - 30. 20.0600 21.9000 - 90. 0.9200 3.8800 - 90. 1.4600 6.4700 - 90. 1.9500 9.0400 - 90. 2.4400 12.6300 - 90. 2.9800 16.2500 - 90. 3.5100 18.3400 - 90. 3.9900 21.6800 - 90. 8.0300 29.5600 - 90. 16.1100 36.7200 - 90. 18.1400 38.2700 - 90. 20.1300 38.1900 - 150. 0.9600 2.7100 - 150. 1.4200 4.2000 - 150. 1.9400 7.5600 - 150. 2.4600 10.4100 - 150. 2.9400 11.5100 - 150. 3.4400 13.6600 - 150. 3.9600 17.9800 - 150. 8.0000 19.2700 - 150. 16.1400 22.9700 - 150. 18.1300 27.9400 - 150. 20.1200 29.5300 +ANG MISC DATA +ADEG MM ARB-UNITS + 30. 5.6 6.37 + 30. 8.4 10.35 + 30. 11.2 15.52 + 30. 14. 17.77 + 30. 16.8 20.87 + 30. 19.6 22.11 + 30. 22.4 23.57 + 30. 44.8 20.51 + 30. 89.6 21.12 + 30. 100.8 22.43 + 30. 112. 21.9 + 90. 5.6 3.88 + 90. 8.4 6.47 + 90. 11.2 9.04 + 90. 14. 12.63 + 90. 16.8 16.25 + 90. 19.6 18.34 + 90. 22.4 21.68 + 90. 44.8 29.56 + 90. 89.6 36.72 + 90. 100.8 38.27 + 90. 112. 38.19 + 150. 5.6 2.71 + 150. 8.4 4.20 + 150. 11.2 7.56 + 150. 14. 10.41 + 150. 16.8 11.51 + 150. 19.6 13.66 + 150. 22.4 17.98 + 150. 44.8 19.27 + 150. 89.6 22.97 + 150. 100.8 27.94 + 150. 112. 29.53 ENDDATA 35 -ENDSUBENT 47 +ENDSUBENT 48 NOSUBENT M0036003 910205 20050926 0000 NOSUBENT M0036004 910205 20050926 0000 -SUBENT M0036005 910204 20050926 0000 +SUBENT M0036005 20110530 20111003 20110921 M059 BIB 1 1 -REACTION (82-PB-0(G,N),,DA,,BRS/REL,EXP) +REACTION (82-PB-0(G,X)0-NN-1,,DA,,BRA/REL) ENDBIB 1 COMMON 1 3 EN-MAX @@ -84,16 +90,16 @@ ENDCOMMON 3 DATA 2 5 ANG DATA ADEG ARB-UNITS - 30.00 4.37 - 60.00 6.08 - 90.00 6.75 - 120.00 5.20 - 165.00 2.07 + 30. 4.37 + 60. 6.08 + 90. 6.75 + 120. 5.2 + 165. 2.07 ENDDATA 7 ENDSUBENT 17 -SUBENT M0036006 910204 20050926 0000 +SUBENT M0036006 20110530 20111003 20110921 M059 BIB 1 1 -REACTION (82-PB-0(G,N),,DA,,BRS/REL,EXP) +REACTION (82-PB-0(G,X)0-NN-1,,DA,,BRA/REL) ENDBIB 1 COMMON 1 3 EN-MAX @@ -103,25 +109,23 @@ ENDCOMMON 3 DATA 2 11 ANG DATA ADEG ARB-UNITS - 0.00 8.61 - 15.00 11.63 - 30.00 15.25 - 45.00 18.54 - 60.00 21.19 - 75.00 23.53 - 90.00 23.97 - 105.00 24.19 - 135.00 20.42 - 150.00 17.23 - 165.00 16.40 + 0.0 8.61 + 15. 11.63 + 30. 15.25 + 45. 18.54 + 60. 21.19 + 75. 23.53 + 90. 23.97 + 105. 24.19 + 135. 20.42 + 150. 17.23 + 165. 16.4 ENDDATA 13 ENDSUBENT 23 -SUBENT M0036007 910205 20050926 0000 -BIB 2 3 -REACTION (82-PB-0(G,N),,DA,,BRS/REL,EXP) -INC-SPECT MAXIMUM PHOTON ENERGY IS EQUAL TO INCIDENT ELECTRON - ENERGY. -ENDBIB 3 +SUBENT M0036007 20110530 20111003 20110921 M059 +BIB 1 1 +REACTION (82-PB-0(G,X)0-NN-1,,DA,,BRA/REL) +ENDBIB 1 COMMON 1 3 EN-MAX MEV @@ -130,74 +134,77 @@ ENDCOMMON 3 DATA 2 12 ANG DATA ADEG ARB-UNITS - 0.00 12.31 - 15.00 15.43 - 30.00 22.55 - 45.00 29.88 - 60.00 33.92 - 75.00 36.53 - 90.00 37.61 - 105.00 36.46 - 120.00 35.05 - 135.00 32.11 - 150.00 28.20 - 165.00 23.64 + 0.0 12.31 + 15. 15.43 + 30. 22.55 + 45. 29.88 + 60. 33.92 + 75. 36.53 + 90. 37.61 + 105. 36.46 + 120. 35.05 + 135. 32.11 + 150. 28.2 + 165. 23.64 ENDDATA 14 -ENDSUBENT 26 -SUBENT M0036008 910205 20050926 0000 -BIB 1 1 -REACTION (82-PB-0(G,N),,TTY/DA,,BRS/REL,EXP) -ENDBIB 1 +ENDSUBENT 24 +SUBENT M0036008 20110530 20111003 20110921 M059 +BIB 2 4 +REACTION (82-PB-0(G,X)0-NN-1,,TTY/DA,,BRA/REL) + Neutron flux density in neutron/sec cm**2. +MISC-COL (MISC) The sample thickness on this subject was + measured and given in radiative lengths (= 5.6 mm). +ENDBIB 4 COMMON 1 3 EN-MAX MEV 200. ENDCOMMON 3 DATA 3 24 -THICKNESS ANG DATA -ARB-UNITS ADEG ARB-UNITS - 1. 30.0000 6.3000 - 1. 45.0000 4.9000 - 1. 75.0000 3.8000 - 1. 90.0000 3.7000 - 1. 105.0000 3.4000 - 1. 120.0000 3.1000 - 1. 136.0000 3.2000 - 1. 151.0000 2.9000 - 1. 161.0000 2.5000 - 2. 30.00 15.00 - 2. 90.00 9.00 - 2. 150.00 8.00 - 3. 28.0000 21.1000 - 3. 91.0000 16.4000 - 3. 151.0000 11.7000 - 4. 30.00 23.00 - 4. 90.00 22.00 - 4. 150.00 18.00 - 8. 30.00 20.00 - 8. 90.00 30.00 - 8. 150.00 20.00 - 16. 30.00 22.00 - 16. 90.00 37.00 - 16. 150.00 23.00 +ANG MISC DATA +ADEG MM ARB-UNITS + 28. 16.8 21.1 + 30. 5.6 6.3 + 30. 11.2 15. + 30. 22.4 23. + 30. 44.8 20. + 30. 89.6 22. + 45. 5.6 4.9 + 75. 5.6 3.8 + 90. 5.6 3.7 + 90. 11.2 9. + 90. 22.4 22. + 90. 44.8 30. + 90. 89.6 37. + 91. 16.8 16.4 + 105. 5.6 3.4 + 120. 5.6 3.1 + 136. 5.6 3.2 + 150. 11.2 8. + 150. 22.4 18. + 150. 44.8 20. + 150. 89.6 23. + 151. 5.6 2.9 + 151. 16.8 11.7 + 161. 5.6 2.5 ENDDATA 26 -ENDSUBENT 36 +ENDSUBENT 39 NOSUBENT M0036009 910205 20050926 0000 NOSUBENT M0036010 910205 20050926 0000 NOSUBENT M0036011 910205 20050926 0000 NOSUBENT M0036012 910205 20050926 0000 NOSUBENT M0036013 910205 20050926 0000 -SUBENT M0036014 910204 20050926 0000 +SUBENT M0036014 20110530 20111003 20110921 M059 BIB 1 1 -REACTION (82-PB-0(G,N),,TTY,,BRS/REL,EXP) +REACTION (82-PB-0(G,X)0-NN-1,,TTY,,BRA/REL) ENDBIB 1 NOCOMMON 0 0 DATA 2 3 EN-MAX DATA MEV ARB-UNITS - 59.0000 11.3000 - 125.0000 17.8000 - 200.0000 17.8000 + 59. 11.3 + 125. 17.8 + 200. 17.8 ENDDATA 5 ENDSUBENT 11 ENDENTRY 14 diff --git a/exforall/M00/M0076.x4 b/exforall/M00/M0076.x4 index b38942926..92be7ad85 100644 --- a/exforall/M00/M0076.x4 +++ b/exforall/M00/M0076.x4 @@ -1,76 +1,82 @@ -ENTRY M0076 910204 20050926 0000 -SUBENT M0076001 910204 20050926 0000 -BIB 13 22 -TITLE PRODUCT YIELDS OF PHOTOFISSION OF PU-239. -AUTHOR (M.YA.KONDRA'TKO,A.V.MOSESOV,K.A.PETRZHAK, - O.A.TEODOROVICH) -INSTITUTE (4CCPTIL) -REFERENCE (J,AE,50,34,81) -FACILITY (LINAC,4CCPTIL) +ENTRY M0076 20110530 20111003 20110921 M059 +SUBENT M0076001 20110530 20111003 20110921 M059 +BIB 13 28 +TITLE Product yields of photofission of Pu-239. +AUTHOR (M.Ya.Kondrat'ko,A.V.Mosesov,K.A.Petrzhak, + O.A.Teodorovich) +INSTITUTE (4RUSTIL) +REFERENCE (J,AE,50,34,1981) + (J,SJA,50,41,1981) + English translation of AE,50,34,1981. +FACILITY (LINAC,4RUSTIL) INC-SOURCE (BRST) METHOD (EXTB,SITA) PART-DET (FF) DETECTOR (GELI) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -STATUS (CURVE) -HISTORY (830329C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -COMMENT IN ORDER TO OBTAIN DATA ON THE MASS AND CHARGE - DISTRIBUTIONS OF THE PRODUCTS OF PHOTOFISSION OF - THE PU-239 NUCLEUS, DETERMINATION OF THE INDEPENDENT - YIELDS OF PHOTOFISSION PRODUCT WAS MADE FOR - BREMSSTRAHLUNG WITH END-POINT ENERGY 28 MEV. THE - INFORMATION ABOUT THE RADIOACTIVE PRODUCTS OF THE - PU-239(G,F) REACTION WAS OBTAINED FROM THE SPECTRA OF - G-QUANTA EMITTED BY THE FRAGMENTS. -ENDBIB 22 +ERR-ANALYS (DATA-ERR) Total errors included statistical + unvertainties and time dependencies analysis. +STATUS (TABLE) Data from Table 1. +HISTORY (19830329C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110530A) Corrected by V.Varlamov: REFERENCE, + INSTITUTE, FACILITY, BRS -> BRA, ELEMENT, dates, + lowercase. +COMMENT In order to obtain data on the mass and charge + distributions of the products of photofission of the + Pu-239 nucleus, determination of the independent + yields of photofission product was made for + bremsstrahlung with end-point energy 28 MeV. The + information about the radioactive products of the + Pu-239(g,f) reaction was obtained from the spectra + of g-quanta emitted by the fragments. +ENDBIB 28 NOCOMMON 0 0 -ENDSUBENT 25 -SUBENT M0076002 910204 20050926 0000 +ENDSUBENT 31 +SUBENT M0076002 20110530 20111003 20110921 M059 BIB 1 1 -REACTION (94-PU-239(G,F)MASS,CUM,FY,,BRS/REL,EXP) +REACTION (94-PU-239(G,F)ELEM/MASS,CUM,FY,,BRA) ENDBIB 1 COMMON 1 3 EN-MAX MEV 28. ENDCOMMON 3 -DATA 3 33 -MASS DATA ERR-S -NO-DIM ARB-UNITS ARB-UNITS - 85. 0.0085 0.0007 - 88. 0.0162 0.0021 - 91. 0.0289 0.0023 - 92. 0.0320 0.0016 - 93. 0.0402 0.0020 - 95. 0.0439 0.0013 - 97. 0.0463 0.0017 - 99. 0.0576 0.0022 - 103. 0.0555 0.0028 - 105. 0.0396 0.0020 - 106. 0.0370 0.0026 - 111. 0.0124 0.0008 - 112. 0.0096 0.0006 - 113. 0.0071 0.0007 - 115. 0.0039 0.0003 - 117. 0.0017 0.0002 - 118. 0.0023 0.0002 - 127. 0.0143 0.0015 - 131. 0.0467 0.0015 - 132. 0.0496 0.0016 - 133. 0.0543 0.0021 - 135. 0.0632 0.0026 - 139. 0.0518 0.0026 - 140. 0.0455 0.0018 - 141. 0.0423 0.0014 - 143. 0.0326 0.0013 - 144. 0.0283 0.0011 - 145. 0.0233 0.0015 - 147. 0.0164 0.0006 - 151. 0.0075 0.0007 - 153. 0.0039 0.0003 - 156. 0.0016 0.0002 - 157. 0.0010 0.0002 +DATA 5 33 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS + 36. 85. 1. .851 .068 + 36. 88. 1.62 .21 + 38. 91. 2.89 .23 + 39. 92. 3.2 .16 + 39. 93. 4.02 .2 + 40. 95. 4.39 .13 + 40. 97. 4.63 .17 + 42. 99. 5.76 .22 + 44. 103. 5.55 .28 + 44. 105. 3.96 .2 + 44. 106. 3.7 .26 + 47. 111. 1.242 .075 + 47. 112. .955 .057 + 47. 113. .710 .069 + 48. 115. 0. .394 .027 + 48. 117. 1. .165 .017 + 48. 117. 0. .227 .016 + 51. 127. 1.43 .15 + 53. 131. 4.67 .15 + 53. 132. 4.96 .16 + 53. 133. 5.43 .21 + 54. 135. 6.32 .26 + 56. 139. 5.18 .26 + 57. 140. 4.55 .18 + 58. 141. 4.23 .14 + 58. 143. 3.26 .13 + 58. 144. 2.83 .11 + 59. 145. 2.33 .15 + 60. 147. 1.642 .064 + 61. 151. .745 .074 + 62. 153. .385 .027 + 62. 156. .161 .018 + 63. 157. .098 .015 ENDDATA 35 ENDSUBENT 45 ENDENTRY 2 diff --git a/exforall/M00/M0081.x4 b/exforall/M00/M0081.x4 index 827a7ee8a..5369fc61e 100644 --- a/exforall/M00/M0081.x4 +++ b/exforall/M00/M0081.x4 @@ -1,103 +1,107 @@ -ENTRY M0081 910204 20050926 0000 -SUBENT M0081001 910204 20050926 0000 -BIB 13 16 -TITLE DEPENDENCE OF U-233 AND PU-239 PHOTOFISSION ASYMMETRY - ON BREMSSTRAHLUNG END-POINT ENERGY. -AUTHOR (M.YA.KONDRAT'KO,V.N.KORINETS,K.A.PETRZHAK) -INSTITUTE (4CCPTIL) -REFERENCE (J,AE,40,72,76) -FACILITY (BETAT,4CCPTIL) +ENTRY M0081 20110530 20111003 20110921 M059 +SUBENT M0081001 20110530 20111003 20110921 M059 +BIB 13 20 +TITLE Dependence of U-233 and Pu-239 photofission asymmetry + on bremsstrahlung end-point energy. +AUTHOR (M.Ya.Kondrat'ko,V.N.Korinets,K.A.Petrzhak) +INSTITUTE (4RUSTIL) +REFERENCE (J,AE,40,72,1976) + (J,SJA,40,83,1976) + English translation of AE,40,72,1976. +FACILITY (BETAT,4RUSTIL) INC-SOURCE (BRST) -METHOD (EXTB,SITA) +METHOD (BSPEC,CHSEP) PART-DET (FF) DETECTOR (D4PI) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -STATUS (CURVE) -HISTORY (830311C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -COMMENT RELATIVE YIELDS OF PU-239 AND U-233 FISSION BY - BREMSSTRAHLUNG BEAMS WERE MEASURED. -ENDBIB 16 +ERR-ANALYS (DATA-ERR) No information. +STATUS (TABLE) Data from Tables 1 and 2. +HISTORY (19830311C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110530A) Corrected by V.Varlamov: REFERENCE, + INSTITUTE, FACILITY, dates, BRS -> BRA, lowercase. +COMMENT Relative yields of Pu-239 and U-233 fission by + bremsstrahlung beams were measured. +ENDBIB 20 NOCOMMON 0 0 -ENDSUBENT 19 -SUBENT M0081002 910204 20050926 0000 +ENDSUBENT 23 +SUBENT M0081002 20110530 20111003 20110921 M059 BIB 1 2 -REACTION ((92-U-233(G,F)47-AG-113,CUM,FY,,BRS,EXP)/ - (92-U-233(G,F)56-BA-140,CUM,FY,,BRS,EXP)) +REACTION ((92-U-233(G,F)47-AG-113,CUM,FY,,BRA)/ + (92-U-233(G,F)56-BA-140,CUM,FY,,BRA)) ENDBIB 2 NOCOMMON 0 0 DATA 3 6 -EN-MAX DATA ERR-S +EN-MAX DATA DATA-ERR MEV NO-DIM NO-DIM 10. 0.0031 0.0008 12. 0.022 0.005 14. 0.037 16. 0.053 20. 0.068 - 24. 0.100 + 24. 0.1 ENDDATA 8 ENDSUBENT 15 -SUBENT M0081003 910204 20050926 0000 +SUBENT M0081003 20110530 20111003 20110921 M059 BIB 1 2 -REACTION ((92-U-233(G,F)48-CD-115,CUM,FY,,BRS,EXP)/ - (92-U-233(G,F)56-BA-140,CUM,FY,,BRS,EXP)) +REACTION ((92-U-233(G,F)48-CD-115,CUM,FY,,BRA)/ + (92-U-233(G,F)56-BA-140,CUM,FY,,BRA)) ENDBIB 2 NOCOMMON 0 0 DATA 3 6 -EN-MAX DATA ERR-S +EN-MAX DATA DATA-ERR MEV NO-DIM NO-DIM - 10. 0.0078 0.0010 + 10. 0.0078 0.001 12. 0.034 0.002 - 14. 0.060 + 14. 0.06 16. 0.068 20. 0.095 24. 0.126 ENDDATA 8 ENDSUBENT 15 -SUBENT M0081004 910204 20050926 0000 +SUBENT M0081004 20110530 20111003 20110921 M059 BIB 1 2 -REACTION ((92-U-233(G,F)48-CD-117,CUM,FY,,BRS,EXP)/ - (92-U-233(G,F)56-BA-140,CUM,FY,,BRS,EXP)) +REACTION ((92-U-233(G,F)48-CD-117,CUM,FY,,BRA)/ + (92-U-233(G,F)56-BA-140,CUM,FY,,BRA)) ENDBIB 2 NOCOMMON 0 0 DATA 3 6 -EN-MAX DATA ERR-S +EN-MAX DATA DATA-ERR MEV NO-DIM NO-DIM 10. 0.005 0.001 12. 0.032 0.002 - 14. 0.060 + 14. 0.06 16. 0.061 20. 0.086 24. 0.128 ENDDATA 8 ENDSUBENT 15 -SUBENT M0081005 910204 20050926 0000 +SUBENT M0081005 20110530 20111003 20110921 M059 BIB 1 2 -REACTION ((94-PU-239(G,F)47-AG-111,CUM,FY,,BRS,EXP)/ - (94-PU-239(G,F)56-BA-140,CUM,FY,,BRS,EXP)) +REACTION ((94-PU-239(G,F)47-AG-111,CUM,FY,,BRA)/ + (94-PU-239(G,F)56-BA-140,CUM,FY,,BRA)) ENDBIB 2 NOCOMMON 0 0 DATA 3 6 -EN-MAX DATA ERR-S +EN-MAX DATA DATA-ERR MEV NO-DIM NO-DIM 10. 0.046 0.005 12. 0.075 0.005 - 14. 0.100 + 14. 0.1 16. 0.144 20. 0.176 24. 0.202 ENDDATA 8 ENDSUBENT 15 -SUBENT M0081006 910204 20050926 0000 +SUBENT M0081006 20110530 20111003 20110921 M059 BIB 1 2 -REACTION ((94-PU-239(G,F)47-AG-113,CUM,FY,,BRS,EXP)/ - (94-PU-239(G,F)56-BA-140,CUM,FY,,BRS,EXP)) +REACTION ((94-PU-239(G,F)47-AG-113,CUM,FY,,BRA)/ + (94-PU-239(G,F)56-BA-140,CUM,FY,,BRA)) ENDBIB 2 NOCOMMON 0 0 DATA 3 6 -EN-MAX DATA ERR-S +EN-MAX DATA DATA-ERR MEV NO-DIM NO-DIM - 10. 0.020 0.006 + 10. 0.02 0.006 12. 0.031 0.003 14. 0.058 16. 0.081 @@ -105,14 +109,14 @@ MEV NO-DIM NO-DIM 24. 0.121 ENDDATA 8 ENDSUBENT 15 -SUBENT M0081007 910204 20050926 0000 +SUBENT M0081007 20110530 20111003 20110921 M059 BIB 1 2 -REACTION ((94-PU-239(G,F)48-CD-115,CUM,FY,,BRS,EXP)/ - (94-PU-239(G,F)56-BA-140,CUM,FY,,BRS,EXP)) +REACTION ((94-PU-239(G,F)48-CD-115,CUM,FY,,BRA)/ + (94-PU-239(G,F)56-BA-140,CUM,FY,,BRA)) ENDBIB 2 NOCOMMON 0 0 DATA 3 6 -EN-MAX DATA ERR-S +EN-MAX DATA DATA-ERR MEV NO-DIM NO-DIM 10. 0.013 0.002 12. 0.027 0.002 @@ -122,16 +126,16 @@ MEV NO-DIM NO-DIM 24. 0.127 ENDDATA 8 ENDSUBENT 15 -SUBENT M0081008 910204 20050926 0000 +SUBENT M0081008 20110530 20111003 20110921 M059 BIB 1 2 -REACTION ((94-PU-239(G,F)48-CD-117,CUM,FY,,BRS,EXP)/ - (94-PU-239(G,F)56-BA-140,CUM,FY,,BRS,EXP)) +REACTION ((94-PU-239(G,F)48-CD-117,CUM,FY,,BRA)/ + (94-PU-239(G,F)56-BA-140,CUM,FY,,BRA)) ENDBIB 2 NOCOMMON 0 0 DATA 3 6 -EN-MAX DATA ERR-S +EN-MAX DATA DATA-ERR MEV NO-DIM NO-DIM - 10. 0.010 0.002 + 10. 0.01 0.002 12. 0.024 0.003 14. 0.049 16. 0.071 diff --git a/exforall/M00/M0082.x4 b/exforall/M00/M0082.x4 index 676248ce4..972f49be9 100644 --- a/exforall/M00/M0082.x4 +++ b/exforall/M00/M0082.x4 @@ -1,29 +1,33 @@ -ENTRY M0082 910204 20050926 0000 -SUBENT M0082001 910204 20050926 0000 -BIB 13 17 -TITLE RELATIVE YIELDS OF XENON ISOTOPES IN NP-237 AND U-235 - PHOTOFISSION. -AUTHOR (K.A.PETRZHAK,E.V.PLATYGINA,YU.A.SOLOV'EV,V.F.TEPLYKH) -INSTITUTE (4CCPTIL) -REFERENCE (J,AE,41,44,76) -FACILITY (BETAT,4CCPTIL) +ENTRY M0082 20110530 20111003 20110921 M059 +SUBENT M0082001 20110530 20111003 20110921 M059 +BIB 13 21 +TITLE Relative yields of xenon isotopes in Np-237 and U-235 + photofission. +AUTHOR (K.A.Petrzhak,E.V.Platygina,Yu.A.Solov'ev,V.F.Teplykh) +INSTITUTE (4RUSTIL) +REFERENCE (J,AE,41,44,1976) + (J,SJA,41,654,1976) + English translation of AE,41,44,1976. +FACILITY (BETAT,4RUSTIL) INC-SOURCE (BRST) METHOD (ASEP) PART-DET (FF) DETECTOR (MAGSP) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -STATUS (CURVE) -HISTORY (830317C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -COMMENT RELATIVE YIELDS OF XENON ISOTOPES WITH A=131-136 IN - PROCESS OF NP-237 AND U-235 FISSION BY BREMSSTRAHLUNG - BEAMS WERE MEASURED. -ENDBIB 17 +ERR-ANALYS (DATA-ERR) No information. +STATUS (TABLE) Data from Table. +HISTORY (19830317C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110530) Corrected by V.Varlamov: dates, REFERENCE, + INSTITUTE, FACILITY, BRS -> BRA, lowercase. +COMMENT Relative yields of xenon isotopes with A = 131-136 in + process of Np-237 and U-235 fission by + bremsstrahlung beams were measured. +ENDBIB 21 NOCOMMON 0 0 -ENDSUBENT 20 -SUBENT M0082002 910204 20050926 0000 +ENDSUBENT 24 +SUBENT M0082002 20110530 20111003 20110921 M059 BIB 1 1 -REACTION (93-NP-237(G,F)ELEM/MASS,CUM,FY,,BRS/REL,EXP) +REACTION (93-NP-237(G,F)ELEM/MASS,CUM,FY,,BRA/REL) ENDBIB 1 COMMON 2 3 EN-MAX ELEMENT @@ -31,17 +35,17 @@ MEV NO-DIM 20. 54. ENDCOMMON 3 DATA 3 4 -MASS DATA ERR-S +MASS DATA DATA-ERR NO-DIM ARB-UNITS ARB-UNITS - 131. 0.215 0.006 - 132. 0.230 0.007 - 134. 0.291 0.005 - 136. 0.264 0.004 + 131. 21.5 .6 + 132. 23. .7 + 134. 29.1 .5 + 136. 26.4 .4 ENDDATA 6 ENDSUBENT 16 -SUBENT M0082003 910204 20050926 0000 +SUBENT M0082003 20110530 20111003 20110921 M059 BIB 1 1 -REACTION (93-NP-237(G,F)ELEM/MASS,CUM,FY,,BRS/REL,EXP) +REACTION (93-NP-237(G,F)ELEM/MASS,CUM,FY,,BRA/REL) ENDBIB 1 COMMON 2 3 EN-MAX ELEMENT @@ -49,17 +53,17 @@ MEV NO-DIM 15. 54. ENDCOMMON 3 DATA 3 4 -MASS DATA ERR-S +MASS DATA DATA-ERR NO-DIM ARB-UNITS ARB-UNITS - 131. 0.197 0.012 - 132. 0.214 0.015 - 134. 0.318 0.011 - 136. 0.271 0.009 + 131. 19.7 1.2 + 132. 21.4 1.5 + 134. 31.8 1.1 + 136. 27.1 .9 ENDDATA 6 ENDSUBENT 16 -SUBENT M0082004 910204 20050926 0000 +SUBENT M0082004 20110530 20111003 20110921 M059 BIB 1 1 -REACTION (92-U-235(G,F)ELEM/MASS,CUM,FY,,BRS/REL,EXP) +REACTION (92-U-235(G,F)ELEM/MASS,CUM,FY,,BRA/REL) ENDBIB 1 COMMON 2 3 EN-MAX ELEMENT @@ -67,12 +71,12 @@ MEV NO-DIM 20. 54. ENDCOMMON 3 DATA 3 4 -MASS DATA ERR-S +MASS DATA DATA-ERR NO-DIM ARB-UNITS ARB-UNITS - 131. 0.200 0.002 - 132. 0.242 0.003 - 134. 0.285 0.002 - 136. 0.273 0.002 + 131. 20. .2 + 132. 24.2 .3 + 134. 28.5 .2 + 136. 27.3 .2 ENDDATA 6 ENDSUBENT 16 ENDENTRY 4 diff --git a/exforall/M00/M0087.x4 b/exforall/M00/M0087.x4 index 350ae6684..b3de907a0 100644 --- a/exforall/M00/M0087.x4 +++ b/exforall/M00/M0087.x4 @@ -1,332 +1,41 @@ -ENTRY M0087 910204 20050926 0000 -SUBENT M0087001 910204 20050926 0000 -BIB 12 17 -TITLE COMPARISON OF CROSS SECTIONS OF CD-115 AND BA-140 - FORMATION IN U-235, U-238, NP-237, AND PU-239 - PHOTOFISSION. -AUTHOR (P.P.GANICH,V.I.LOMONOSOV,D.I.SIKORA) -INSTITUTE (4CCPTIL) -REFERENCE (J,AE,48,36,80) -FACILITY (BETAT,4CCPTIL) +ENTRY M0087 20110530 20111003 20110921 M059 +SUBENT M0087001 20110530 20111003 20110921 M059 +BIB 12 23 +TITLE Comparison of cross sections of Cd-115 and Ba-140 + formation in U-235, U-238, Np-237, and Pu-239 + photofission. +AUTHOR (P.P.Ganich,V.I.Lomonosov,D.I.Sikora) +INSTITUTE (4RUSTIL) +REFERENCE (J,AE,48,36,1980) + (J,SJA,48,45,1980) + English translation of AE,48,36,1980. +FACILITY (BETAT,4RUSTIL) INC-SOURCE (BRST) METHOD (REC,STTA) PART-DET (FF) DETECTOR (GELI) (D4PI) STATUS (CURVE) -HISTORY (830510C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -COMMENT YIELD FISSION FRAGMENTS OF THE BA-140 AND CD-113 - WERE MEASURED. -ENDBIB 17 +COMMENT Yields of the Ba-140 and Cd-113 fission fragments + were measured. +HISTORY (19830510C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110530A) Corrected by V.Varlamov: REFERENCE, + INSTITUTE, FACILITY, dates, lowercase. + (20110818A) ENTRY deleted because there are no + experimental data. +ENDBIB 23 NOCOMMON 0 0 -ENDSUBENT 20 -SUBENT M0087002 910204 20050926 0000 -BIB 2 2 -REACTION (92-U-235(G,F),CHG,FY,,BRS/REL,EXP) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -ENDBIB 2 -NOCOMMON 0 0 -DATA 3 15 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 6.0 0.0 - 8.4 0.8 - 10.0 2.2 - 11.3 4.2 - 12.5 7.2 1.0 - 13.5 10.6 - 14.5 14.1 1.5 - 15.6 17.9 - 16.6 21.0 1.2 - 17.4 23.1 - 18.5 25.3 1.0 - 19.5 27.0 - 20.4 28.3 - 21.4 29.4 - 22.0 30.1 -ENDDATA 17 -ENDSUBENT 24 -SUBENT M0087003 910204 20050926 0000 -BIB 2 2 -REACTION (92-U-238(G,F),CHG,FY,,BRS/REL,EXP) -ERR-ANALYS NO INFORMATION -ENDBIB 2 -NOCOMMON 0 0 -DATA 2 18 -EN-MAX DATA -MEV ARB-UNITS - 6.0 0.0 - 7.3 0.5 - 8.1 0.7 - 9.7 1.4 - 10.7 2.3 - 11.6 3.3 - 12.4 4.7 - 13.0 6.0 - 13.6 7.2 - 14.2 8.7 - 14.7 9.9 - 15.3 11.2 - 15.8 12.5 - 16.4 13.9 - 16.9 15.1 - 17.5 16.3 - 18.3 17.4 - 19.0 18.2 -ENDDATA 20 -ENDSUBENT 27 -SUBENT M0087004 910204 20050926 0000 -BIB 2 2 -REACTION (93-NP-237(G,F),CHG,FY,,BRS/REL,EXP) -ERR-ANALYS NO INFORMATION -ENDBIB 2 -NOCOMMON 0 0 -DATA 2 16 -EN-MAX DATA -MEV ARB-UNITS - 6.0 0.0 - 7.2 0.7 - 8.6 2.0 - 10.3 4.7 - 11.5 7.7 - 12.6 11.6 - 13.4 14.6 - 14.2 17.7 - 15.1 21.0 - 16.0 24.3 - 16.8 27.3 - 17.5 29.6 - 18.4 32.3 - 19.6 35.0 - 20.6 36.5 - 21.2 37.3 -ENDDATA 18 -ENDSUBENT 25 -SUBENT M0087005 910204 20050926 0000 -BIB 2 2 -REACTION (94-PU-239(G,F),CHG,FY,,BRS/REL,EXP) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -ENDBIB 2 -NOCOMMON 0 0 -DATA 3 19 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 6.0 0.0 - 7.8 1.7 - 9.1 3.0 - 9.9 4.8 1.0 - 10.9 9.1 - 11.6 12.7 - 12.0 15.6 1.5 - 12.6 21.1 - 13.2 25.4 - 13.9 31.0 2.5 - 14.8 38.0 - 15.6 43.1 - 16.3 47.8 - 17.0 52.1 - 17.8 56.4 - 18.5 60.3 - 19.3 64.6 - 20.0 67.7 - 21.1 71.4 -ENDDATA 21 -ENDSUBENT 28 -SUBENT M0087006 910204 20050926 0000 -BIB 2 2 -REACTION (92-U-235(G,F)56-BA-140,CUM,FY,,BRS/REL,EXP) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -ENDBIB 2 -NOCOMMON 0 0 -DATA 3 17 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 6.0 0.0 - 7.1 0.4 - 8.9 1.4 - 10.2 2.9 0.2 - 11.3 5.3 - 11.9 6.9 1.0 - 13.0 10.5 - 13.9 13.1 0.2 - 14.8 16.2 - 15.7 18.8 - 16.2 20.2 0.7 - 17.2 22.6 - 18.0 24.3 0.2 - 19.0 26.3 - 20.0 27.8 - 21.0 29.1 - 22.0 30.0 -ENDDATA 19 -ENDSUBENT 26 -SUBENT M0087007 910204 20050926 0000 -BIB 2 2 -REACTION (92-U-235(G,F)48-CD-115,CUM,FY,,BRS/REL,EXP) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -ENDBIB 2 -NOCOMMON 0 0 -DATA 3 15 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 10.0 0.5 - 11.5 1.5 - 11.9 2.0 0.7 - 13.2 4.1 - 14.1 6.6 - 15.0 9.0 - 15.8 11.8 - 16.7 14.8 - 17.5 17.4 - 18.2 19.7 - 18.9 22.1 - 19.6 24.1 - 20.3 26.1 - 21.0 27.9 - 22.0 30.0 -ENDDATA 17 -ENDSUBENT 24 -SUBENT M0087008 910204 20050926 0000 -BIB 2 2 -REACTION (92-U-238(G,F)56-BA-140,CUM,FY,,BRS/REL,EXP) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -ENDBIB 2 -NOCOMMON 0 0 -DATA 3 17 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 6.0 0.0 - 7.0 0.4 - 8.1 0.9 0.2 - 9.3 1.6 - 10.4 2.4 - 11.4 3.6 - 12.1 4.8 0.5 - 12.9 6.5 - 13.6 7.9 - 14.2 9.5 0.1 - 14.9 11.0 - 15.6 12.6 - 16.1 13.8 0.2 - 16.9 15.3 - 17.6 16.4 - 18.4 17.5 0.2 - 19.1 18.2 -ENDDATA 19 ENDSUBENT 26 -SUBENT M0087009 910204 20050926 0000 -BIB 2 2 -REACTION (92-U-238(G,F)48-CD-115,CUM,FY,,BRS/REL,EXP) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -ENDBIB 2 -NOCOMMON 0 0 -DATA 3 20 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 10.0 0.2 - 11.3 0.6 - 11.9 0.9 0.3 - 13.0 1.7 - 13.9 2.9 - 14.5 3.8 - 15.1 5.1 - 15.6 6.2 - 16.2 7.4 - 16.7 8.7 - 17.1 9.8 - 17.4 10.7 - 17.8 11.7 - 18.2 12.8 - 18.7 14.0 - 19.2 15.5 - 19.7 16.7 - 20.2 18.0 - 20.7 19.3 - 20.9 20.0 -ENDDATA 22 -ENDSUBENT 29 -SUBENT M0087010 910204 20050926 0000 -BIB 2 2 -REACTION (93-NP-237(G,F)56-BA-140,CUM,FY,,BRS/REL,EXP) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -ENDBIB 2 -NOCOMMON 0 0 -DATA 3 16 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 6.0 0.0 - 7.1 1.0 - 8.2 2.1 - 9.0 3.2 0.1 - 10.2 5.4 - 11.1 7.8 - 12.1 11.1 0.3 - 13.3 15.7 - 14.1 19.0 0.9 - 15.3 23.2 - 16.4 27.2 0.8 - 17.6 30.9 - 18.5 33.6 - 19.4 35.8 - 20.6 37.3 1.0 - 21.3 37.9 -ENDDATA 18 -ENDSUBENT 25 -SUBENT M0087011 910204 20050926 0000 -BIB 2 2 -REACTION (93-NP-237(G,F)48-CD-115,CUM,FY,,BRS/REL,EXP) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -ENDBIB 2 -NOCOMMON 0 0 -DATA 3 20 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 8.9 0.0 - 10.4 1.0 - 11.3 2.0 - 12.0 3.0 0.7 - 13.1 5.2 - 14.0 7.4 - 14.7 10.0 - 15.3 12.3 - 15.9 14.6 - 16.4 17.2 - 16.9 19.3 - 17.3 21.4 - 17.9 24.3 - 18.3 26.1 - 18.7 27.7 - 19.2 29.5 - 19.6 31.0 - 20.0 32.6 - 20.8 35.1 - 21.3 36.9 -ENDDATA 22 -ENDSUBENT 29 -SUBENT M0087012 910204 20050926 0000 -BIB 2 2 -REACTION (94-PU-239(G,F)48-CD-115,CUM,FY,,BRS/REL,EXP) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -ENDBIB 2 -NOCOMMON 0 0 -DATA 3 14 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 10.0 0.9 - 12.0 4.1 1.5 - 13.0 9.2 - 13.9 15.0 2.0 - 14.7 21.9 - 15.3 26.9 - 16.0 32.2 - 16.6 37.7 - 17.3 43.5 - 18.0 48.4 - 18.8 54.7 - 19.4 59.7 - 20.2 64.9 - 20.7 69.1 -ENDDATA 16 -ENDSUBENT 23 +NOSUBENT M0087002 20110530 20111003 20110921 M059 +NOSUBENT M0087003 20110530 20111003 20110921 M059 +NOSUBENT M0087004 20110530 20111003 20110921 M059 +NOSUBENT M0087005 20110530 20111003 20110921 M059 +NOSUBENT M0087006 20110530 20111003 20110921 M059 +NOSUBENT M0087007 20110530 20111003 20110921 M059 +NOSUBENT M0087008 20110530 20111003 20110921 M059 +NOSUBENT M0087009 20110530 20111003 20110921 M059 +NOSUBENT M0087010 20110530 20111003 20110921 M059 +NOSUBENT M0087011 20110530 20111003 20110921 M059 +NOSUBENT M0087012 20110530 20111003 20110921 M059 ENDENTRY 12 diff --git a/exforall/M00/M0089.x4 b/exforall/M00/M0089.x4 index b4034fd51..231a6ce35 100644 --- a/exforall/M00/M0089.x4 +++ b/exforall/M00/M0089.x4 @@ -1,126 +1,134 @@ -ENTRY M0089 910204 20050926 0000 -SUBENT M0089001 910204 20050926 0000 -BIB 13 17 -TITLE YIELDS OF NP-237 PHOTOFISSION PRODUCTS. -AUTHOR (M.YA.KONDRAT'KO,A.V.MOSESOV,K.A.PETRZHAK, - O.A.TEODOROVICH) -INSTITUTE (4CCPTIL) -REFERENCE (J,AE,53,164,82) -FACILITY (LINAC,4CCPTIL) +ENTRY M0089 20110531 20111003 20110921 M059 +SUBENT M0089001 20110531 20111003 20110921 M059 +BIB 13 22 +TITLE Yields of Np-237 photofission products. +AUTHOR (M.Ya.Kondrat'ko,A.V.Mosesov,K.A.Petrzhak, + O.A.Teodorovich) +INSTITUTE (4RUSTIL) +REFERENCE (J,AE,53,164,1982) + (J,SJA,53,629,1982) + English translation of AE,53,164,1982. +FACILITY (LINAC,4RUSTIL) INC-SOURCE (BRST) METHOD (REC,STTA) PART-DET (FF) DETECTOR (GELI) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ONLY. -STATUS (CURVE) -HISTORY (830512C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -COMMENT MASS DISTRIBUTIONS OF THE NP-237 FISSION FRAGMENTS AT - THE BREMSSTRAHLUNG END-POINTS ENERGIES 22,25 AND 28 MEV - BEAM WERE MEASURED. -ENDBIB 17 +ERR-ANALYS (DATA-ERR) No information. +STATUS (TABLE) Data from Table 1. +HISTORY (19830512C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: REFERENCE, + INSTITUTE, FACILITY, ELEMENT, PC/FIS, BRS -> BRA, + dates, lowercase. +COMMENT Mass distributions of the Np-237 fission fragments at + the bremsstrahlung beam end-points energies 22, 25 + and 28 MeV were measured. +ENDBIB 22 NOCOMMON 0 0 -ENDSUBENT 20 -SUBENT M0089002 910204 20050926 0000 +ENDSUBENT 25 +SUBENT M0089002 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRS/REL,EXP) +REACTION (93-NP-237(G,F)ELEM/MASS,CUM,FY,,BRA) ENDBIB 1 COMMON 1 3 EN-MAX MEV 22. ENDCOMMON 3 -DATA 3 5 -MASS DATA ERR-S -NO-DIM NO-DIM NO-DIM - 111. 0.594 0.036 - 112. 0.492 0.019 - 115. 0.319 0.017 - 117. 0.211 0.018 - 140. 4.9 0.18 -ENDDATA 7 -ENDSUBENT 17 -SUBENT M0089003 910204 20050926 0000 +DATA 5 6 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS + 47. 111. .594 .036 + 47. 112. .492 .019 + 48. 115. .319 .017 + 48. 117. 1. .096 .005 + 48. 117. .211 .018 + 57. 140. 4.9 .18 +ENDDATA 8 +ENDSUBENT 18 +SUBENT M0089003 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRS/REL,EXP) +REACTION (93-NP-237(G,F)ELEM/MASS,CUM,FY,,BRA) ENDBIB 1 COMMON 1 3 EN-MAX MEV 25. ENDCOMMON 3 -DATA 3 22 -MASS DATA ERR-S -NO-DIM NO-DIM NO-DIM - 85. 1.02 0.06 - 88. 2.41 0.25 - 91. 4.07 0.22 - 92. 4.46 0.18 - 93. 4.81 0.17 - 95. 5.31 0.21 - 97. 5.45 0.16 - 99. 5.89 0.21 - 103. 4.47 0.28 - 105. 2.39 0.21 - 109. 0.91 0.06 - 111. 0.701 0.056 - 112. 0.492 0.042 - 127. 1.44 0.1 - 129. 1.95 1.14 - 131. 4.41 0.15 - 132. 4.72 0.13 - 133. 5.57 0.25 - 135. 6.57 0.19 - 136. 0.507 0.065 - 140. 4.88 0.17 - 143. 3.66 0.14 +DATA 5 22 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS + 36. 85. 1. 1.02 .06 + 36. 88. 2.41 .25 + 38. 91. 4.07 .22 + 39. 92. 4.45 .18 + 39. 93. 4.81 .17 + 40. 95. 5.31 .21 + 40. 97. 5.45 .16 + 42. 99. 5.89 .21 + 44. 103. 4.47 .28 + 45. 105. 2.39 .21 + 46. 109. .91 .06 + 47. 111. .701 .056 + 47. 112. .492 .042 + 51. 127. 1.44 .1 + 51. 129. 1.95 1.14 + 53. 131. 4.41 .15 + 53. 132. 0. 4.72 .13 + 53. 133. 5.57 .25 + 54. 135. 6.57 .19 + 55. 136. .507 .065 + 57. 140. 4.88 .17 + 58. 143. 3.66 .14 ENDDATA 24 ENDSUBENT 34 -SUBENT M0089004 910204 20050926 0000 +SUBENT M0089004 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRS/REL,EXP) +REACTION (93-NP-237(G,F)ELEM/MASS,CUM,FY,,BRA) ENDBIB 1 COMMON 1 3 EN-MAX MEV 28. ENDCOMMON 3 -DATA 3 33 -MASS DATA ERR-S -NO-DIM NO-DIM NO-DIM - 85. 1.15 0.11 - 88. 2.20 0.24 - 91. 4.02 0.21 - 92. 4.03 0.32 - 93. 4.59 0.21 - 95. 5.26 0.15 - 97. 5.54 0.16 - 99. 5.9 0.23 - 103. 4.39 0.17 - 105. 2.66 0.12 - 106. 2.56 0.23 - 111. 0.665 0.04 - 112. 0.575 0.033 - 115. 0.46 0.028 - 117. 0.271 0.021 - 127. 1.49 0.06 - 129. 1.97 1.12 - 131. 4.53 0.14 - 132. 4.66 0.12 - 133. 5.49 0.2 - 135. 6.28 0.18 - 136. 0.538 0.021 - 140. 4.87 0.14 - 141. 4.59 0.26 - 143. 3.73 0.13 - 144. 3.31 0.19 - 145. 2.87 0.17 - 147. 1.864 0.059 - 149. 1.496 0.096 - 151. 0.722 0.045 - 153. 0.38 0.022 - 156. 0.115 0.013 - 157. 0.068 0.01 -ENDDATA 35 -ENDSUBENT 45 +DATA 5 35 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS + 36. 85. 1. 1.15 .11 + 36. 88. 2.2 .24 + 38. 91. 4.02 .21 + 39. 92. 4.03 .32 + 39. 93. 4.59 .21 + 40. 95. 5.26 .15 + 40. 97. 5.54 .16 + 42. 99. 5.9 .23 + 44. 103. 4.39 .17 + 44. 106. 2.56 .23 + 45. 105. 2.66 .12 + 46. 111. .665 .04 + 46. 112. .575 .033 + 48. 115. .46 .028 + 48. 117. 1. .124 .007 + 48. 117. 0. .271 .021 + 51. 127. 1.49 .06 + 51. 129. 1.97 .12 + 53. 131. 4.53 .14 + 53. 132. 1. .2 .13 + 53. 132. 0. 4.66 .12 + 53. 133. 5.49 .2 + 54. 135. 6.28 .18 + 55. 136. .538 .021 + 57. 140. 4.87 .14 + 58. 141. 4.59 .26 + 58. 143. 3.73 .13 + 58. 144. 3.31 .19 + 59. 145. 2.87 .17 + 60. 147. 1.864 .059 + 61. 149. 1.496 .096 + 61. 151. .722 .045 + 62. 153. .38 .022 + 62. 156. .115 .013 + 63. 157. .068 .01 +ENDDATA 37 +ENDSUBENT 47 ENDENTRY 4 diff --git a/exforall/M01/M0172.x4 b/exforall/M01/M0172.x4 index e698cff0e..9aa36bc1f 100644 --- a/exforall/M01/M0172.x4 +++ b/exforall/M01/M0172.x4 @@ -1,46 +1,84 @@ -ENTRY M0172 910205 20050926 0000 -SUBENT M0172001 910205 20050926 0000 -BIB 12 14 -TITLE RADIOCHEMICAL INVESTIGATION OF RARE-EARTH GROUP - ELEMENTS YIELDS IN U-238 PHOTOFISSION. -AUTHOR (K.A.PETRZHAK,P.V.SEDLETSKIY) -INSTITUTE (4CCPTIL) -REFERENCE (J,AE,15,308,63) -FACILITY (BETAT,4CCPTIL) +ENTRY M0172 20110531 20111003 20110921 M059 +SUBENT M0172001 20110531 20111003 20110921 M059 +BIB 14 31 +TITLE Radiochemical investigation of rare-earth group + elements yields in U-238 photofission. +AUTHOR (K.A.Petrzhak,P.V.Sedletskiy) +INSTITUTE (4RUSTIL) +REFERENCE (J,AE,15,308,1963) + (J,SJA,15,1025,1963) + English translation of AE,15,308,1963. +FACILITY (BETAT,4RUSTIL) INC-SOURCE (BRST) -METHOD (EXTB,SITA,CHSEP) +METHOD (BSPEC,CHSEP) PART-DET (FF) DETECTOR (GEMUC,D4PI) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS GIVEN. -STATUS (CURVE) -HISTORY (870807C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 14 +ANALYSIS (DECAY) +ERR-ANALYS (DATA-ERR) No information. +DECAY-DATA (39-Y-93,11.0HR) + (44-RU-103,39.8D) + (44-RU-105,4.4HR) + (47-AG-111,7.6D) + (47-AG-113,5.3HR) + (57-LA-141,3.7HR) + (58-CE-143,33.4HR) + (59-PR-145,6.0HR) + (60-ND-147,11.3D) + (60-ND-149,1.8HR) + (61-PM-151,27.5HR) +STATUS (TABLE)Table 1 of AE,15,308,1963 +HISTORY (19870807C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: REFERENCE, + INSTITUTE, FACILITY, dates, BRS -> BRA, ELEMENT, + DATA-ERR, DECAY-DATA, SUBENT 003 added, lowercase. +ENDBIB 31 COMMON 1 3 EN-MAX MEV 14. ENDCOMMON 3 -ENDSUBENT 21 -SUBENT M0172002 910205 20050926 0000 +ENDSUBENT 38 +SUBENT M0172002 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (92-U-238(G,F)MASS,CHN,FY,,BRS,EXP) +REACTION (92-U-238(G,F)ELEM/MASS,CUM,FY,,BRA) ENDBIB 1 NOCOMMON 0 0 -DATA 5 11 -MASS DATA ERR-S HL HL -NO-DIM PC/FIS PC/FIS HR D - 93. 4.3 0.4 11. - 103. 4.11 0.12 39.8 - 105. 3.59 0.09 4.4 - 111. 0.27 0.11 7.6 - 113. 0.28 0.11 5.3 - 141. 6.2 0.9 3.7 - 143. 4.3 33.4 - 145. 4.2 0.7 6.0 - 147. 4.4 1.2 11.3 - 149. 2.2 0.5 1.8 - 151. 1.1 0.2 27.5 +DATA 4 11 +ELEMENT MASS DATA DATA-ERR +NO-DIM NO-DIM PC/FIS PC/FIS + 39. 93. 4.3 0.4 + 44. 103. 4.11 0.12 + 44. 105. 3.59 0.09 + 47. 111. 0.27 0.11 + 47. 113. 0.28 0.11 + 57. 141. 6.2 0.9 + 58. 143. 4.3 + 59. 145. 4.2 0.7 + 60. 147. 4.4 1.2 + 60. 149. 2.2 0.5 + 61. 151. 1.1 0.2 ENDDATA 13 ENDSUBENT 19 -ENDENTRY 2 +SUBENT M0172003 20110531 20111003 20110921 M059 +BIB 1 2 +REACTION ((92-U-238(G,F)ELEM/MASS,CUM,FY,,BRA)/ + (92-U-238(G,F)58-CE-143,CUM,FY,,BRA)) +ENDBIB 2 +NOCOMMON 0 0 +DATA 4 10 +ELEMENT MASS DATA DATA-ERR +NO-DIM NO-DIM NO-DIM NO-DIM + 39. 93. .996 .096 + 44. 103. .955 .028 + 44. 105. .832 .02 + 47. 111. .064 .025 + 47. 113. .066 .025 + 57. 141. 1.45 .21 + 59. 145. .989 .167 + 60. 147. 1.03 .28 + 60. 149. .52 .12 + 61. 151. .25 .05 +ENDDATA 12 +ENDSUBENT 19 +ENDENTRY 3 diff --git a/exforall/M01/M0177.x4 b/exforall/M01/M0177.x4 index 3b23ebdf4..03b38bc85 100644 --- a/exforall/M01/M0177.x4 +++ b/exforall/M01/M0177.x4 @@ -1,101 +1,110 @@ -ENTRY M0177 910205 20050926 0000 -SUBENT M0177001 910205 20050926 0000 -BIB 12 14 -TITLE DEPENDENCE OF THE U-235 PHOTOFISSION ASYMMETRY ON - BREMSSTRAHLUNG END-POINT ENERGY. -AUTHOR (M.YA.KONDRAT'KO,K.A.PETRZHAK) -INSTITUTE (4CCPTIL) -REFERENCE (J,AE,20,514,66) -FACILITY (BETAT,4CCPTIL) +ENTRY M0177 20110531 20111003 20110921 M059 +SUBENT M0177001 20110531 20111003 20110921 M059 +BIB 12 19 +TITLE Dependence of the U-235 photofission asymmetry on + bremsstrahlung end-point energy. +AUTHOR (M.Ya.Kondrat'ko,K.A.Petrzhak) +INSTITUTE (4RUSTIL) +REFERENCE (J,AE,20,514,1966) + (J,SJA,20,594,1966) + English translation of AE,20,514,1966. +FACILITY (BETAT,4RUSTIL) INC-SOURCE (BRST) -METHOD (EXTB,SITA,CHSEP) +METHOD (BSPEC,CHSEP) PART-DET (FF) DETECTOR (D4PI) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS GIVEN. -STATUS (CURVE) -HISTORY (870807C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 14 +ERR-ANALYS (DATA-ERR) No information. +STATUS (TABLE) +HISTORY (19870807C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: REFERENCE, + INSTITUTE, FACILITY, dates, BRS -> BRA, DATA-ERR, + lowercase. +ENDBIB 19 NOCOMMON 0 0 -ENDSUBENT 17 -SUBENT M0177002 910205 20050926 0000 -BIB 3 3 -REACTION (92-U-235(G,F)56-BA-135,CUM,FY,,BRS/REL,EXP) -MONITOR (92-U-235(G,F)48-CD-115-M,CHN,FY,,BRA,EXP) -DECAY-MON (48-CD-115-M,53.HR) -ENDBIB 3 +ENDSUBENT 22 +SUBENT M0177002 20110531 20111003 20110921 M059 +BIB 3 4 +REACTION ((92-U-235(G,F)56-BA-139,CUM,FY,,BRA)/ + (92-U-235(G,F)48-CD-115,CUM,FY,,BRA)) +MONITOR (92-U-235(G,F)48-CD-115,CHN,FY,,BRA) +DECAY-MON (48-CD-115,53.HR) +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 10.0 131.0 28.0 - 12.0 52.2 8.3 - 14.0 30.8 3.4 - 16.0 21.6 2.4 - 18.0 20.3 2.8 - 20.0 13.7 1.1 - 22.0 13.2 1.7 +EN-MAX DATA DATA-ERR +MEV NO-DIM NO-DIM + 10. 131. 28. + 12. 52.2 8.3 + 14. 30.8 3.4 + 16. 21.6 2.4 + 18. 20.3 2.8 + 20. 13.7 1.1 + 22. 13.2 1.7 25.2 11.3 1.6 ENDDATA 10 -ENDSUBENT 18 -SUBENT M0177003 910205 20050926 0000 -BIB 3 3 -REACTION (92-U-235(G,F)56-BA-140,CUM,FY,,BRS/REL,EXP) -MONITOR (92-U-235(G,F)48-CD-115-M,CHN,FY,,BRA,EXP) -DECAY-MON (48-CD-115-M,53.HR) -ENDBIB 3 +ENDSUBENT 19 +SUBENT M0177003 20110531 20111003 20110921 M059 +BIB 3 4 +REACTION ((92-U-235(G,F)56-BA-140,CUM,FY,,BRA)/ + (92-U-235(G,F)48-CD-115,CUM,FY,,BRA)) +MONITOR (92-U-235(G,F)48-CD-115,CHN,FY,,BRA) +DECAY-MON (48-CD-115,53.HR) +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 10.0 124.0 22.0 - 12.0 50.8 8.1 - 14.0 28.5 3.2 - 16.0 20.4 1.9 - 18.0 16.5 1.7 - 20.0 13.6 1.0 - 22.0 11.9 1.3 +EN-MAX DATA DATA-ERR +MEV NO-DIM NO-DIM + 10. 124. 22. + 12. 50.8 8.1 + 14. 28.5 3.2 + 16. 20.4 1.9 + 18. 16.5 1.7 + 20. 13.6 1. + 22. 11.9 1.3 25.2 10.3 0.9 ENDDATA 10 -ENDSUBENT 18 -SUBENT M0177004 910205 20050926 0000 -BIB 3 3 -REACTION (92-U-235(G,F)56-BA-139,CUM,FY,,BRS/REL,EXP) -MONITOR (92-U-235(G,F)48-CD-117-M,CHN,FY,,BRA,EXP) +ENDSUBENT 19 +SUBENT M0177004 20110531 20111003 20110921 M059 +BIB 3 4 +REACTION ((92-U-235(G,F)56-BA-139,CUM,FY,,BRA)/ + (92-U-235(G,F)48-CD-117-M,CUM,FY,,BRA)) +MONITOR (92-U-235(G,F)48-CD-117-M,CHN,FY,,BRA) DECAY-MON (48-CD-117-M,3.HR) -ENDBIB 3 +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 10.0 134. 25. - 12.0 60.1 8.0 - 14.0 35.6 2.1 - 16.0 26.4 2.0 - 18.0 22.7 2.4 - 20.0 17.0 0.9 - 22.0 16.7 1.4 +EN-MAX DATA DATA-ERR +MEV NO-DIM NO-DIM + 10. 134. 25. + 12. 60.1 8. + 14. 35.6 2.1 + 16. 26.4 2. + 18. 22.7 2.4 + 20. 17. 0.9 + 22. 16.7 1.4 25.2 15.6 1.9 ENDDATA 10 -ENDSUBENT 18 -SUBENT M0177005 910205 20050926 0000 -BIB 3 3 -REACTION (92-U-235(G,F)56-BA-140,CUM,FY,,BRS/REL,EXP) -MONITOR (92-U-235(G,F)48-CD-117-M,CHN,FY,,BRA,EXP) +ENDSUBENT 19 +SUBENT M0177005 20110531 20111003 20110921 M059 +BIB 3 4 +REACTION ((92-U-235(G,F)56-BA-140,CUM,FY,,BRA)/ + (92-U-235(G,F)48-CD-117-M,CUM,FY,,BRA)) +MONITOR (92-U-235(G,F)48-CD-117-M,CHN,FY,,BRA) DECAY-MON (48-CD-117-M,3.HR) -ENDBIB 3 +ENDBIB 4 NOCOMMON 0 0 DATA 3 8 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 10.0 127. 18. - 12.0 58.5 7.9 - 14.0 33.1 1.8 - 16.0 25.0 1.1 - 18.0 18.5 0.9 - 20.0 16.9 0.8 - 22.0 15.0 0.7 +EN-MAX DATA DATA-ERR +MEV NO-DIM NO-DIM + 10. 127. 18. + 12. 58.5 7.9 + 14. 33.1 1.8 + 16. 25. 1.1 + 18. 18.5 0.9 + 20. 16.9 0.8 + 22. 15. 0.7 25.2 14.2 0.7 ENDDATA 10 -ENDSUBENT 18 +ENDSUBENT 19 ENDENTRY 5 diff --git a/exforall/M01/M0178.x4 b/exforall/M01/M0178.x4 index d2f27a179..970577e8e 100644 --- a/exforall/M01/M0178.x4 +++ b/exforall/M01/M0178.x4 @@ -1,70 +1,233 @@ -ENTRY M0178 910205 20050926 0000 -SUBENT M0178001 910205 20050926 0000 -BIB 12 13 -TITLE DELAYED NEUTRONS IN PHOTOFISSION OF HEAVY NUCLEI. -AUTHOR (O.P.NIKOTIN,K.A.PETRZHAK) -INSTITUTE (4CCPTIL) -REFERENCE (J,AE,20,268,66) -FACILITY (BETAT,4CCPTIL) +ENTRY M0178 20110531 20111003 20110921 M059 +SUBENT M0178001 20110531 20111003 20110921 M059 +BIB 12 19 +TITLE Delayed neutrons in photofission of heavy nuclei. +AUTHOR (O.P.Nikotin,K.A.Petrzhak) +INSTITUTE (4RUSTIL) +REFERENCE (J,AE,20,268,1966) + (J,SJA,20,300,1966) + English translation of AE,20,268,1966. +FACILITY (BETAT,4RUSTIL) INC-SOURCE (BRST) METHOD (EXTB,SITA) PART-DET (FF) DETECTOR (PROPC) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS GIVEN. +ERR-ANALYS (ERR-S) Statistical errors given. STATUS (CURVE) -HISTORY (870807C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 13 +HISTORY (19870807C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: REFERENCE, + INSTITUTE, FACILITY, BRS -> BRA, dates, data in 002 + redigitized, 003-005 deleted because 1 point in arb. + units, 006-013 added, lowercase. +ENDBIB 19 NOCOMMON 0 0 -ENDSUBENT 16 -SUBENT M0178002 910205 20050926 0000 -BIB 1 1 -REACTION (92-U-238(G,F),DL,NU,,BRS/REL,EXP) -ENDBIB 1 +ENDSUBENT 22 +SUBENT M0178002 20110531 20111003 20110921 M059 +BIB 1 2 +REACTION (92-U-238(G,F),DL,NU,,BRA/REL) + Total yields in %. +ENDBIB 2 NOCOMMON 0 0 DATA 3 7 EN-MAX DATA ERR-S MEV ARB-UNITS ARB-UNITS - 10. 2.97 0.04 - 12.2 2.95 0.04 - 13.5 3.04 0.04 - 14.2 2.88 0.04 - 14.5 2.70 0.04 - 15. 3.1 0.04 - 15.5 3.26 0.04 + 10. 97.49 4.14 + 12.2 95.52 3.62 + 13.5 98.19 3.79 + 14.2 93.4 4.25 + 14.5 90.51 5. + 15. 100. 3.29 + 15.5 104.9 3.1 ENDDATA 9 -ENDSUBENT 15 -SUBENT M0178003 910205 20050926 0000 +ENDSUBENT 16 +SUBENT M0178003 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (90-TH-232(G,F),DL,NU,,BRS/REL,EXP) +REACTION (90-TH-232(G,F),DL,NU,,BRA/REL) ENDBIB 1 NOCOMMON 0 0 -DATA 3 1 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 15. 3.8 0.6 -ENDDATA 3 -ENDSUBENT 9 -SUBENT M0178004 910205 20050926 0000 +NODATA 0 0 +ENDSUBENT 5 +SUBENT M0178004 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (92-U-235(G,F),DL,NU,,BRS/REL,EXP) +REACTION (92-U-235(G,F),DL,NU,,BRA/REL) ENDBIB 1 NOCOMMON 0 0 -DATA 3 1 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 15. 0.96 0.13 -ENDDATA 3 -ENDSUBENT 9 -SUBENT M0178005 910205 20050926 0000 +NODATA 0 0 +ENDSUBENT 5 +SUBENT M0178005 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (94-PU-239(G,F),DL,NU,,BRS/REL,EXP) +REACTION (94-PU-239(G,F),DL,NU,,BRA/REL) ENDBIB 1 NOCOMMON 0 0 -DATA 3 1 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 15. 0.36 0.06 -ENDDATA 3 -ENDSUBENT 9 -ENDENTRY 5 +NODATA 0 0 +ENDSUBENT 5 +SUBENT M0178006 20110531 20111003 20110921 M059 +BIB 1 3 +REACTION ((90-TH-232(G,F),DL/GRP,NU,,BRA)/ + (90-TH-232(G,F),DL,NU,,BRA)) + Relative yieds in %. +ENDBIB 3 +COMMON 1 3 +EN-MAX +MEV + 15.0 +ENDCOMMON 3 +DATA 5 6 +HL DATA ERR-S -ERR-S +ERR-S +SEC ARB-UNITS ARB-UNITS ARB-UNITS ARB-UNITS + 55.6 4.4 .2 + 20.3 16.3 1. + 5.45 15.9 1.5 + 1.98 37.5 3. + .43 17.2 2. + .18 8.7 4. 2. +ENDDATA 8 +ENDSUBENT 20 +SUBENT M0178007 20110531 20111003 20110921 M059 +BIB 1 3 +REACTION ((92-U-235(G,F),DL/GRP,NU,,BRA)/ + (92-U-235(G,F),DL,NU,,BRA)) + Relative yields in %. +ENDBIB 3 +COMMON 1 3 +EN-MAX +MEV + 15.0 +ENDCOMMON 3 +DATA 5 6 +HL DATA ERR-S -ERR-S +ERR-S +SEC ARB-UNITS ARB-UNITS ARB-UNITS ARB-UNITS + 54.7 5.4 .5 + 20.3 20. 2. + 5.45 15.2 2. + 2.01 36.9 4. + .5 13.9 2. + .19 8.6 5. 2. +ENDDATA 8 +ENDSUBENT 20 +SUBENT M0178008 20110531 20111003 20110921 M059 +BIB 1 3 +REACTION ((92-U-238(G,F),DL/GRP,NU,,BRA)/ + (92-U-238(G,F),DL,NU,,BRA)) + Relative yields in %. +ENDBIB 3 +COMMON 1 3 +EN-MAX +MEV + 15.0 +ENDCOMMON 3 +DATA 5 6 +HL DATA ERR-S -ERR-S +ERR-S +SEC ARB-UNITS ARB-UNITS ARB-UNITS ARB-UNITS + 56.2 1.98 .08 + 21.3 15.7 .5 + 5.5 17.5 .7 + 2.15 31.1 .8 + .7 17.7 .9 + .19 16.1 5. 2. +ENDDATA 8 +ENDSUBENT 20 +SUBENT M0178009 20110531 20111003 20110921 M059 +BIB 1 3 +REACTION ((94-PU-239(G,F),DL/GRP,NU,,BRA)/ + (94-PU-238(G,F),DL,NU,,BRA)) + Relative yields in %. +ENDBIB 3 +COMMON 1 3 +EN-MAX +MEV + 15.0 +ENDCOMMON 3 +DATA 5 6 +HL DATA ERR-S -ERR-S +ERR-S +SEC ARB-UNITS ARB-UNITS ARB-UNITS ARB-UNITS + 54. 6.05 .6 + 20.6 20.6 2. + 5.7 18.3 3. + 1.94 29.5 4. + .58 14.9 3. + .2 10.6 5. 2. +ENDDATA 8 +ENDSUBENT 20 +SUBENT M0178010 20110531 20111003 20110921 M059 +BIB 1 1 +REACTION (90-TH-232(G,F),DL/GRP,NU,,BRA) +ENDBIB 1 +COMMON 1 3 +EN-MAX +MEV + 15.0 +ENDCOMMON 3 +DATA 5 6 +HL DATA ERR-S -ERR-S +ERR-S +SEC PC/FIS PC/FIS PC/FIS PC/FIS + 55.6 .17 .03 + 20.3 .62 .1 + 5.45 .6 .1 + 1.98 1.43 .3 + .43 .66 .1 + .18 .33 .2 .1 +ENDDATA 8 +ENDSUBENT 18 +SUBENT M0178011 20110531 20111003 20110921 M059 +BIB 1 1 +REACTION (92-U-235(G,F),DL/GRP,NU,,BRA) +ENDBIB 1 +COMMON 1 3 +EN-MAX +MEV + 15.0 +ENDCOMMON 3 +DATA 5 6 +HL DATA ERR-S -ERR-S +ERR-S +SEC PC/FIS PC/FIS PC/FIS PC/FIS + 54.7 .052 .01 + 20.3 .193 .04 + 5.45 .146 .03 + 2.01 .354 .07 + .5 .134 .03 + .19 .083 .05 .025 +ENDDATA 8 +ENDSUBENT 18 +SUBENT M0178012 20110531 20111003 20110921 M059 +BIB 1 1 +REACTION (92-U-238(G,F),DL/GRP,NU,,BRA) +ENDBIB 1 +COMMON 1 3 +EN-MAX +MEV + 15.0 +ENDCOMMON 3 +DATA 5 6 +HL DATA ERR-S -ERR-S +ERR-S +SEC PC/FIS PC/FIS PC/FIS PC/FIS + 56.2 .061 .01 + 21.3 .489 .07 + 5.5 .545 .07 + 2.15 .97 .15 + .7 .552 .08 + .19 .502 .2 .12 +ENDDATA 8 +ENDSUBENT 18 +SUBENT M0178013 20110531 20111003 20110921 M059 +BIB 1 1 +REACTION (94-PU-239(G,F),DL/GRP,NU,,BRA) +ENDBIB 1 +COMMON 1 3 +EN-MAX +MEV + 15.0 +ENDCOMMON 3 +DATA 5 6 +HL DATA ERR-S -ERR-S +ERR-S +SEC PC/FIS PC/FIS PC/FIS PC/FIS + 54. .022 .004 + 20.6 .075 .018 + 5.7 .066 .015 + 1.94 .105 .02 + .58 .054 .012 + .2 .038 .025 .012 +ENDDATA 8 +ENDSUBENT 18 +ENDENTRY 13 diff --git a/exforall/M01/M0186.x4 b/exforall/M01/M0186.x4 index c5d549c4f..d06e4df8d 100644 --- a/exforall/M01/M0186.x4 +++ b/exforall/M01/M0186.x4 @@ -1,6 +1,6 @@ -ENTRY M0186 20110316 20110617 20110530 M058 -SUBENT M0186001 20110316 20110617 20110530 M058 -BIB 11 21 +ENTRY M0186 20110607 20111003 20110921 M059 +SUBENT M0186001 20110607 20111003 20110921 M059 +BIB 11 23 TITLE Photofission of even-even nuclei and structure of fission barrier. AUTHOR (S.P.Kapitza,N.S.Rabotnov,G.N.Smirenkin,A.S.Soldatov, @@ -15,16 +15,18 @@ PART-DET (FF) DETECTOR (GLASD) STATUS (CURVE) Data from Fig. 2. HISTORY (19870807C) - (19910202A) Corrected by V.Varlamov, V.Mclane + (19910202A) Corrected by V.Varlamov, V.McLane (20110127A) Corrected by V.Varlamov: REFERENCE, dates, CCP -> RUS, ANALYSIS and STATUS in SUBENTs 007 - 011, BRS ->BRA, REACTIONs and DATA recompiled, lowercase. (20110316U) Corrected by V.Varlamov: REFERENCE, typos in SUBENTs 012 - 021. -ENDBIB 21 + (20110607A) Corrected by V.Varlamov: previous HISTORY + line - only typos, not REFERENCE. +ENDBIB 23 NOCOMMON 0 0 -ENDSUBENT 24 +ENDSUBENT 26 SUBENT M0186002 20110127 20110323 20110311 M056 BIB 2 2 REACTION (90-TH-232(G,F),PRE,FY,,BRA/REL) @@ -279,7 +281,7 @@ MEV MB 7.45 2.2E+01 ENDDATA 20 ENDSUBENT 29 -SUBENT M0186012 20110316 20110617 20110530 M058 +SUBENT M0186012 20110607 20111003 20110921 M059 BIB 2 11 REACTION (90-TH-232(G,F),,DA,FF,S2T/BRS/MSC) b/a ratio from expression for angular @@ -319,7 +321,7 @@ MEV NO-DIM 7.1 2.81 ENDDATA 18 ENDSUBENT 38 -SUBENT M0186013 20110316 20110617 20110530 M058 +SUBENT M0186013 20110607 20111003 20110921 M059 BIB 2 11 REACTION (92-U-238(G,F),,DA,FF,S2T/BRS/MSC) b/a ratio from expression for angular @@ -359,7 +361,7 @@ MEV NO-DIM 6.6 .9 ENDDATA 18 ENDSUBENT 38 -SUBENT M0186014 20110316 20110617 20110530 M058 +SUBENT M0186014 20110607 20111003 20110921 M059 BIB 2 11 REACTION (94-PU-238(G,F),,DA,FF,S2T/BRS/MSC) b/a ratio from expression for angular @@ -398,7 +400,7 @@ MEV NO-DIM 6.6 .19 ENDDATA 17 ENDSUBENT 37 -SUBENT M0186015 20110316 20110617 20110530 M058 +SUBENT M0186015 20110607 20111003 20110921 M059 BIB 2 11 REACTION (94-PU-240(G,F),,DA,FF,S2T/BRS/MSC) b/a ratio from expression for angular @@ -434,7 +436,7 @@ MEV NO-DIM 6.1 .1 ENDDATA 14 ENDSUBENT 34 -SUBENT M0186016 20110316 20110617 20110530 M058 +SUBENT M0186016 20110607 20111003 20110921 M059 BIB 2 11 REACTION (94-PU-242(G,F),,DA,FF,S2T/BRS/MSC) b/a ratio from expression for angular @@ -473,7 +475,7 @@ MEV NO-DIM 6.35 .34 ENDDATA 17 ENDSUBENT 37 -SUBENT M0186017 20110316 20110617 20110530 M058 +SUBENT M0186017 20110607 20111003 20110921 M059 BIB 2 12 REACTION (90-TH-232(G,F),,DA,FF,S2T/BRS/MSC) c/b ratio from expression for angular @@ -508,7 +510,7 @@ MEV NO-DIM 6.15 .025 ENDDATA 12 ENDSUBENT 33 -SUBENT M0186018 20110316 20110617 20110530 M058 +SUBENT M0186018 20110607 20111003 20110921 M059 BIB 2 12 REACTION (92-U-238(G,F),,DA,FF,S2T/BRS/MSC) c/b ratio from expression for angular @@ -539,7 +541,7 @@ MEV NO-DIM 5.6 .016 ENDDATA 8 ENDSUBENT 29 -SUBENT M0186019 20110316 20110617 20110530 M058 +SUBENT M0186019 20110607 20111003 20110921 M059 BIB 2 12 REACTION (94-PU-238(G,F),,DA,FF,S2T/BRS/MSC) c/b ratio from expression for angular @@ -574,7 +576,7 @@ MEV NO-DIM 6.05 .13 ENDDATA 12 ENDSUBENT 33 -SUBENT M0186020 20110316 20110617 20110530 M058 +SUBENT M0186020 20110607 20111003 20110921 M059 BIB 2 12 REACTION (94-PU-240(G,F),,DA,FF,S2T/BRS/MSC) c/b ratio from expression for angular @@ -611,7 +613,7 @@ MEV NO-DIM 6.1 .11 ENDDATA 14 ENDSUBENT 35 -SUBENT M0186021 20110316 20110617 20110530 M058 +SUBENT M0186021 20110607 20111003 20110921 M059 BIB 2 12 REACTION (94-PU-242(G,F),,DA,FF,S2T/BRS/MSC) c/b ratio from expression for angular diff --git a/exforall/M01/M0198.x4 b/exforall/M01/M0198.x4 index ac5d23d55..915add5df 100644 --- a/exforall/M01/M0198.x4 +++ b/exforall/M01/M0198.x4 @@ -1,26 +1,32 @@ -ENTRY M0198 910205 20050926 0000 -SUBENT M0198001 910205 20050926 0000 -BIB 12 14 -TITLE THE FRAGMENT YIELDS IN NP-237 PHOTOFISSION. -AUTHOR (M.YA.KONDRAT'KO,V.N.KORINETS,K.A.PETRZHAK, - O.A.TEODOROVICH) -INSTITUTE (4CCPTIL) -REFERENCE (J,AE,35,211,73) -FACILITY (BETAT,4CCPTIL) +ENTRY M0198 20110531 20111003 20110921 M059 +SUBENT M0198001 20110531 20111003 20110921 M059 +BIB 12 20 +TITLE The fragment yields in Np-237 photofission. +AUTHOR (M.Ya.Kondrat'ko,V.N.Korinets,K.A.Petrzhak, + O.A.Teodorovich) +INSTITUTE (4RUSTIL) +REFERENCE (J,AE,35,211,1973) + (J,SJA,35,862,1973) + English translation of AE,35,211,1973. +FACILITY (BETAT,4RUSTIL) INC-SOURCE (BRST) -METHOD (EXTB,SITA,CHSEP) +METHOD (BSPEC,CHSEP) PART-DET (FF) DETECTOR (GEMUC) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS GIVEN. -STATUS (CURVE) -HISTORY (870807C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 14 +ERR-ANALYS (DATA-ERR) Statistical + normalization errors given. +STATUS (TABLE) Data from Table 1 of AE,35,211,1973. +HISTORY (19870807C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: REFERENCE, + INSTITUTE, FACILITY, dates, BRS -> BRA, cumulative + data for 121,125Sn from SUBENT 005 are moved into + SUBENT 008, ELEMENT, lowercase. +ENDBIB 20 NOCOMMON 0 0 -ENDSUBENT 17 -SUBENT M0198002 910205 20050926 0000 +ENDSUBENT 23 +SUBENT M0198002 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRS,EXP) +REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRA) ENDBIB 1 COMMON 1 3 EN-MAX @@ -28,12 +34,12 @@ MEV 24. ENDCOMMON 3 DATA 3 10 -MASS DATA ERR-S +MASS DATA DATA-ERR NO-DIM PC/FIS PC/FIS 103. 4.47 0.35 105. 2.65 0.18 - 109. 1.20 0.11 - 111. 0.70 0.06 + 109. 1.2 0.11 + 111. 0.7 0.06 112. 0.55 0.05 113. 0.51 0.04 115. 0.56 0.04 @@ -42,9 +48,9 @@ NO-DIM PC/FIS PC/FIS 140. 4.82 0.24 ENDDATA 12 ENDSUBENT 22 -SUBENT M0198003 910205 20050926 0000 +SUBENT M0198003 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRS,EXP) +REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRA) ENDBIB 1 COMMON 1 3 EN-MAX @@ -52,23 +58,23 @@ MEV 20. ENDCOMMON 3 DATA 3 10 -MASS DATA ERR-S +MASS DATA DATA-ERR NO-DIM PC/FIS PC/FIS 103. 4.88 0.87 105. 2.87 0.18 109. 0.88 0.09 111. 0.53 0.04 112. 0.47 0.04 - 113. 0.40 0.03 + 113. 0.4 0.03 115. 0.43 0.03 - 117. 0.40 0.03 + 117. 0.4 0.03 139. 6.02 0.35 140. 4.83 0.24 ENDDATA 12 ENDSUBENT 22 -SUBENT M0198004 910205 20050926 0000 +SUBENT M0198004 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRS,EXP) +REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRA) ENDBIB 1 COMMON 1 3 EN-MAX @@ -76,31 +82,37 @@ MEV 16. ENDCOMMON 3 DATA 3 8 -MASS DATA ERR-S +MASS DATA DATA-ERR NO-DIM PC/FIS PC/FIS - 109. 0.73 0.06 - 111. 0.47 0.03 - 112. 0.31 0.03 - 113. 0.31 0.03 - 115. 0.33 0.03 - 117. 0.32 0.03 - 139. 5.64 0.33 - 140. 4.96 0.23 + 109. 0.73 0.06 + 111. 0.47 0.03 + 112. 0.31 0.03 + 113. 0.31 0.03 + 115. 0.33 0.03 + 117. 0.32 0.03 + 139. 5.64 0.33 + 140. 4.96 0.23 ENDDATA 10 ENDSUBENT 20 -SUBENT M0198005 910205 20050926 0000 -BIB 1 1 -REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRS,EXP) -ENDBIB 1 +SUBENT M0198005 20110531 20111003 20110921 M059 +BIB 2 6 +REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRA) +FLAG (1.) Total yield calculated for complete 83As + transition (69 sec) into 83Se. + (2.) Total yield calculated for complete 83As + transition (25 min) into 83Se with coscequent + decay (2.4 h) into 83Br. +ENDBIB 6 COMMON 1 3 EN-MAX MEV 14. ENDCOMMON 3 -DATA 3 24 -MASS DATA ERR-S -NO-DIM PC/FIS PC/FIS - 83. 0.86 0.06 +DATA 4 23 +MASS DATA DATA-ERR FLAG +NO-DIM PC/FIS PC/FIS NO-DIM + 83. 0.76 0.05 1. + 83. 0.86 0.06 2. 91. 2.55 0.18 92. 4.76 0.48 97. 6.23 0.66 @@ -113,22 +125,20 @@ NO-DIM PC/FIS PC/FIS 113. 0.21 0.02 115. 0.22 0.02 117. 0.21 0.02 - 121. 0.21 0.05 - 125. 0.32 0.03 127. 1.36 0.08 129. 2.18 0.21 - 131. 3.90 0.27 - 133. 6.54 0.40 + 131. 3.9 0.27 + 133. 6.54 0.4 135. 4.91 0.33 139. 6.08 0.36 - 140. 4.90 0.20 + 140. 4.9 0.2 141. 4.99 0.31 143. 4.06 0.42 -ENDDATA 26 -ENDSUBENT 36 -SUBENT M0198006 910205 20050926 0000 +ENDDATA 25 +ENDSUBENT 40 +SUBENT M0198006 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRS,EXP) +REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRA) ENDBIB 1 COMMON 1 3 EN-MAX @@ -136,12 +146,12 @@ MEV 12. ENDCOMMON 3 DATA 3 10 -MASS DATA ERR-S +MASS DATA DATA-ERR NO-DIM PC/FIS PC/FIS 103. 4.72 0.84 105. 2.34 0.34 - 109. 0.40 0.07 - 111. 0.20 0.02 + 109. 0.4 0.07 + 111. 0.2 0.02 112. 0.13 0.02 113. 0.11 0.02 115. 0.12 0.02 @@ -150,9 +160,9 @@ NO-DIM PC/FIS PC/FIS 140. 4.94 0.25 ENDDATA 12 ENDSUBENT 22 -SUBENT M0198007 910205 20050926 0000 +SUBENT M0198007 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRS,EXP) +REACTION (93-NP-237(G,F)MASS,CHN,FY,,BRA) ENDBIB 1 COMMON 1 3 EN-MAX @@ -160,10 +170,10 @@ MEV 10. ENDCOMMON 3 DATA 3 8 -MASS DATA ERR-S +MASS DATA DATA-ERR NO-DIM PC/FIS PC/FIS 109. 0.22 0.03 - 111. 0.095 0.010 + 111. 0.095 0.01 112. 0.031 0.008 113. 0.027 0.005 115. 0.032 0.008 @@ -172,4 +182,20 @@ NO-DIM PC/FIS PC/FIS 140. 4.98 0.26 ENDDATA 10 ENDSUBENT 20 -ENDENTRY 7 +SUBENT M0198008 20110531 20111003 20110921 M059 +BIB 1 1 +REACTION (93-NP-237(G,F)ELEM/MASS,CUM,FY,,BRA) +ENDBIB 1 +COMMON 1 3 +EN-MAX +MEV + 14. +ENDCOMMON 3 +DATA 4 2 +ELEMENT MASS DATA DATA-ERR +NO-DIM NO-DIM PC/FIS PC/FIS + 50. 121. 0.21 0.05 + 50. 125. 0.32 0.03 +ENDDATA 4 +ENDSUBENT 14 +ENDENTRY 8 diff --git a/exforall/M01/M0199.x4 b/exforall/M01/M0199.x4 index e8c15ecb8..6928aa8e3 100644 --- a/exforall/M01/M0199.x4 +++ b/exforall/M01/M0199.x4 @@ -1,41 +1,46 @@ -ENTRY M0199 910205 20050926 0000 -SUBENT M0199001 910205 20050926 0000 -BIB 12 14 -TITLE THE FRAGMENTS MASS DISTRIBUTION IN REGION OF SYMMETRY - PHOTOFISSION OF U-235 AND NP-237. -AUTHOR (M.YA.KONDRAT'KO,V.N.KORINETS,K.A.PETRZHAK) -INSTITUTE (4CCPTIL) -REFERENCE (J,AE,35,214,73) -FACILITY (BETAT,4CCPTIL) +ENTRY M0199 20110531 20111003 20110921 M059 +SUBENT M0199001 20110531 20111003 20110921 M059 +BIB 12 19 +TITLE The fragments mass distribution in region of symmetry + photofission of U-235 and Np-237. +AUTHOR (M.Ya.Kondrat'ko,V.N.Korinets,K.A.Petrzhak) +INSTITUTE (4RUSTIL) +REFERENCE (J,AE,35,214,1973) + (J,SJA,35,866,1973) + English translation of AE,35,214,1973. +FACILITY (BETAT,4RUSTIL) INC-SOURCE (BRST) METHOD (EXTB,SITA,CHSEP) PART-DET (FF) DETECTOR (GEMUC) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS GIVEN. -STATUS (CURVE) -HISTORY (870807C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 14 +ERR-ANALYS (DATA-ERR) No information. +STATUS (TABLE) Data from Table. +HISTORY (19870807C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: REFERENCE, + INSTITUTE, FACILITY, BRS -> BRA, ELEMENT, DATA-ERR, + dates, lowercase. +ENDBIB 19 COMMON 1 3 EN-MAX MEV 14.0 ENDCOMMON 3 -ENDSUBENT 21 -SUBENT M0199002 910205 20050926 0000 +ENDSUBENT 26 +SUBENT M0199002 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (92-U-235(G,F)MASS,CHN,FY,,BRS,EXP) +REACTION (92-U-235(G,F)ELEM/MASS,CHN,FY,,BRA) ENDBIB 1 NOCOMMON 0 0 1 -DATA 3 6 -MASS DATA ERR-S -NO-DIM PC/FIS PC/FIS - 109.0 0.292 0.030 - 111.0 0.189 0.020 - 112.0 0.142 0.013 - 113.0 0.170 0.020 - 115.0 0.224 0.020 - 117.0 0.218 0.021 +DATA 4 6 +ELEMENT MASS DATA DATA-ERR +NO-DIM NO-DIM PC/FIS PC/FIS + 46. 109. 0.292 0.03 + 46. 112. 0.142 0.013 + 47. 111. 0.189 0.02 + 47. 113. 0.17 0.02 + 48. 115. 0.224 0.02 + 48. 117. 0.218 0.021 ENDDATA 8 ENDSUBENT 14 ENDENTRY 2 diff --git a/exforall/M02/M0201.x4 b/exforall/M02/M0201.x4 index 414adf4cf..fb5b3aa19 100644 --- a/exforall/M02/M0201.x4 +++ b/exforall/M02/M0201.x4 @@ -1,37 +1,43 @@ -ENTRY M0201 910206 20050926 0000 -SUBENT M0201001 910206 20050926 0000 -BIB 11 25 -TITLE PHOTONUCLEAR REACTION YIELDS ISOMER RATIOS FOR - GAMMA-ACTIVATIONAL ANALYSIS. -AUTHOR (M.G.DAVYDOV,V.G.MAGERA,A.V.TRUKHOV,E.M.SHOMURODOV) -INSTITUTE (4CCPRGU) -REFERENCE (J,AE,58,47,85) -FACILITY (BETAT,4CCPRGU) 22 MEV. +ENTRY M0201 20110531 20111003 20110921 M059 +SUBENT M0201001 20110531 20111003 20110921 M059 +BIB 12 31 +TITLE Isomeric ratios of the photonuclear reactions yields + for gamma-activation analysis. +AUTHOR (M.G.Davydov,V.G.Magera,A.V.Trukhov,E.M.Shomurodov) +INSTITUTE (4RUSRGU) +REFERENCE (J,AE,58,47,1985) + (J,SJA,58,56,1985) + English translation of AE,58,47,1985. +FACILITY (BETAT,4RUSRGU) 22 MeV. INC-SOURCE (BRST) -DETECTOR (NAICR) GAMMA SPECTRA AND DECAY CURVES MEASURED USING - (GELI) EITHER A NAI(TL) CRYSTAL SPECTROMETER OR A - GE(LI) SPECTROMETER. +DETECTOR (NAICR,GELI) Gamma spectra and decay curves measured + using either a NaI(Tl) crystal spectrometer or a + Ge(Li) spectrometer. METHOD (ACTIV) - THE ISOMERIC YIELD RATIOS FOR PHOTONUCLEAR REACTIONS - SC-45(G,N)SC-44, CO-59(G,N)CO-58, SE-74,82(G,N)SE-73, - 81, BR-81(G,N)BR-80, RB-85(G,N)RB-84, SR-86(G,N)SR-85, - ZR-90(G,N)ZR-89, MO-98(G,P)NB-97, CD-116(G,N)CD-115, - SN-112,118(G,P)IN-111,117 HAVE BEEN MEASURED, USING - THE METHOD OF DIRECT COMPARISON OF NUMBERS OF COUNTS - IN GAMMA-LINE PHOTOPEAKS FOR TRANSITIONS TO METASTABLE - AND GROUND STATES AND METHOD OF DECOMPOSITION OF YIELD - CURVES FOR DECAY OR ACTIVATION, MEASURED FOR ANY - GAMMA LINE. -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ARE PRESENTED. -STATUS (APRVD) DATA ARE PUBLISHED IN FORM OF TABLES. -HISTORY (870727C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 25 +ERR-ANALYS (ERR-S) Statistical errors are presented. +STATUS (TABLE) Data from Table. +COMMENT The isomeric yield ratios for photonuclear reactions + Sc-45(g,n)Sc-44, Co-59(g,n)Co-58, + Se-74,82(g,n)Se-73,81, Br-81(g,n)Br-80, + Rb-85(g,n)Rb-84, Sr-86(g,n)Sr-85, Zr-90(g,n)Zr-89, + Mo-98(g,p)Nb-97, Cd-116(g,n)Cd-115, + Sn-112,118(g,p)In-111,117 have been measured, using + the method of direct comparison of numbers of counts + in gamma-line photopeaks for transitions to + metastable and ground states and method of + decomposition of yield curves for decay or + activation, measured for any gamma line. +HISTORY (19870727C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: TITLE, + REFERENCE, INSTITUTE, FACILITY, STATUS, COMMENT, + dates, BRA -> BRS, lowercase. +ENDBIB 31 NOCOMMON 0 0 -ENDSUBENT 28 -SUBENT M0201002 910206 20050926 0000 +ENDSUBENT 34 +SUBENT M0201002 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (21-SC-45(G,N)21-SC-44-M/G,,SIG/RAT,,BRA,EXP) +REACTION (21-SC-45(G,N)21-SC-44-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 @@ -40,9 +46,9 @@ MEV NO-DIM NO-DIM 22. 0.23 0.02 ENDDATA 3 ENDSUBENT 9 -SUBENT M0201003 910206 20050926 0000 +SUBENT M0201003 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (27-CO-59(G,N)27-CO-58-M/G,,SIG/RAT,,BRA,EXP) +REACTION (27-CO-59(G,N)27-CO-58-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 @@ -51,9 +57,9 @@ MEV NO-DIM NO-DIM 22. 0.92 0.02 ENDDATA 3 ENDSUBENT 9 -SUBENT M0201004 910206 20050926 0000 +SUBENT M0201004 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (34-SE-82(G,N)34-SE-81-M/G,,SIG/RAT,,BRA,EXP) +REACTION (34-SE-82(G,N)34-SE-81-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 @@ -62,9 +68,9 @@ MEV NO-DIM NO-DIM 22. 0.54 0.03 ENDDATA 3 ENDSUBENT 9 -SUBENT M0201005 910206 20050926 0000 +SUBENT M0201005 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (34-SE-74(G,N)34-SE-73-M/G,,SIG/RAT,,BRA,EXP) +REACTION (34-SE-74(G,N)34-SE-73-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 @@ -73,9 +79,9 @@ MEV NO-DIM NO-DIM 22. 0.10 0.02 ENDDATA 3 ENDSUBENT 9 -SUBENT M0201006 910206 20050926 0000 +SUBENT M0201006 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (35-BR-81(G,N)35-BR-80-M/G,,SIG/RAT,,BRA,EXP) +REACTION (35-BR-81(G,N)35-BR-80-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 @@ -84,9 +90,9 @@ MEV NO-DIM NO-DIM 22. 0.48 0.03 ENDDATA 3 ENDSUBENT 9 -SUBENT M0201007 910206 20050926 0000 +SUBENT M0201007 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (37-RB-85(G,N)37-RB-84-M/G,,SIG/RAT,,BRA,EXP) +REACTION (37-RB-85(G,N)37-RB-84-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 @@ -95,9 +101,9 @@ MEV NO-DIM NO-DIM 22. 0.31 0.02 ENDDATA 3 ENDSUBENT 9 -SUBENT M0201008 910206 20050926 0000 +SUBENT M0201008 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (38-SR-86(G,N)38-SR-85-M/G,,SIG/RAT,,BRA,EXP) +REACTION (38-SR-86(G,N)38-SR-85-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 @@ -106,9 +112,9 @@ MEV NO-DIM NO-DIM 22. 0.14 0.02 ENDDATA 3 ENDSUBENT 9 -SUBENT M0201009 910206 20050926 0000 +SUBENT M0201009 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (40-ZR-90(G,N)40-ZR-89-M/G,,SIG/RAT,,BRA,EXP) +REACTION (40-ZR-90(G,N)40-ZR-89-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 @@ -117,9 +123,9 @@ MEV NO-DIM NO-DIM 22. 1.44 0.02 ENDDATA 3 ENDSUBENT 9 -SUBENT M0201010 910206 20050926 0000 +SUBENT M0201010 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (42-MO-98(G,P)41-NB-97-M/G,,SIG/RAT,,BRA,EXP) +REACTION (42-MO-98(G,P)41-NB-97-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 @@ -128,9 +134,9 @@ MEV NO-DIM NO-DIM 22. 0.71 0.02 ENDDATA 3 ENDSUBENT 9 -SUBENT M0201011 910206 20050926 0000 +SUBENT M0201011 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (48-CD-116(G,N)48-CD-115-M/G,,SIG/RAT,,BRA,EXP) +REACTION (48-CD-116(G,N)48-CD-115-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 @@ -139,9 +145,9 @@ MEV NO-DIM NO-DIM 22. 0.12 0.02 ENDDATA 3 ENDSUBENT 9 -SUBENT M0201012 910206 20050926 0000 +SUBENT M0201012 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (50-SN-112(G,P)49-IN-111-M/G,,SIG/RAT,,BRA,EXP) +REACTION (50-SN-112(G,P)49-IN-111-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 @@ -150,9 +156,9 @@ MEV NO-DIM NO-DIM 22. 0.044 0.001 ENDDATA 3 ENDSUBENT 9 -SUBENT M0201013 910206 20050926 0000 +SUBENT M0201013 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (50-SN-118(G,P)49-IN-117-M/G,,SIG/RAT,,BRA,EXP) +REACTION (50-SN-118(G,P)49-IN-117-M/G,,SIG/RAT,,BRS) ENDBIB 1 NOCOMMON 0 0 DATA 3 1 diff --git a/exforall/M02/M0202.x4 b/exforall/M02/M0202.x4 index 05a1d1c9d..83cabda30 100644 --- a/exforall/M02/M0202.x4 +++ b/exforall/M02/M0202.x4 @@ -1,39 +1,44 @@ -ENTRY M0202 910206 20050926 0000 -SUBENT M0202001 910206 20050926 0000 -BIB 13 18 -TITLE YIELD OF PU-242 PHOTOFISSION FRAGMENTS. -AUTHOR (VO DAK BANG,YU.S.ZAMYATNIN,CHAN DYK TKHIEN, - CHAN DAI NGIEN ,FAN TKHU KHYONG,LE TKHI KAT TYONG) +ENTRY M0202 20110531 20111003 20110921 M059 +SUBENT M0202001 20110531 20111003 20110921 M059 +BIB 13 23 +TITLE Yield of Pu-242 photofission fragments. +AUTHOR (Vo Dak Bang,Yu.S.Zamyatnin,Chan Dyk Tkhien, + Chan Dai Ngien,Fan Tkhu Khyong,Le Tkhi Kat Tyong) INSTITUTE (4ZZZDUB) -REFERENCE (J,AE,58,275,85) +REFERENCE (J,AE,58,275,1985) + (J,SJA,58,320,1985) + English translation of AE,58,275,1985. FACILITY (MICRT,4ZZZDUB) INC-SOURCE (BRST) METHOD (EXTB,SITA) DETECTOR (GELI) PART-DET (FF) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ARE PRESENTED. -COMMENT THE POSTNEUTRON YIELDS OF PU-242 PHOTOFISSION FRAGMENTS - FOR BREMSSTRAHLUNG OF ELECTRONS WITH ENERGIES 18.1(0.2) - MEV AND 20.7(0.3) MEV AND PARAMETERS OF FRAGMENT MASS - DISTRIBUTION HAVE BEEN MEASURED FOR THE FIRST TIME. -STATUS (TABLE). DATA ARE PUBLISHED IN FORM OF THE TABLE. -HISTORY (870727C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 18 +ERR-ANALYS (DATA-ERR) No information. +COMMENT The postneutron yields of Pu-242 photofission + fragments for bremsstrahlung of electrons with + energies 18.1(0.2) MeV and 20.7(0.3) MeV and + parameters of fragment mass distribution have been + measured for the first time. +STATUS (TABLE) Data from Table 1 and 2. +HISTORY (19870727C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: REFERENCE, dates, + DATA-ERR, PRD/FIS, 003 from Table 2, lowercase. +ENDBIB 23 NOCOMMON 0 0 -ENDSUBENT 21 -SUBENT M0202002 910206 20050926 0000 +ENDSUBENT 26 +SUBENT M0202002 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (94-PU-242(G,F)ELEM/MASS,CUM,FY,,BRA/REL,EXP) +REACTION (94-PU-242(G,F)ELEM/MASS,CUM,FY,,BRA) ENDBIB 1 COMMON 1 3 -EN +EN-MAX MEV 18.1 ENDCOMMON 3 DATA 6 22 -MASS ELEMENT ELEMENT ISOMER DATA ERR-S -NO-DIM NO-DIM NO-DIM NO-DIM ARB-UNITS ARB-UNITS +MASS ELEMENT ELEMENT ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM NO-DIM PRD/FIS PRD/FIS 85. 36. 1. 0.76E-2 0.05E-2 87. 36. 1.04E-2 0.12E-2 88. 36. 37. 1.26E-2 0.28E-2 @@ -58,18 +63,18 @@ NO-DIM NO-DIM NO-DIM NO-DIM ARB-UNITS ARB-UNITS 153. 62. 1.03E-2 0.08E-2 ENDDATA 24 ENDSUBENT 34 -SUBENT M0202003 910206 20050926 0000 +SUBENT M0202003 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (94-PU-242(G,F)ELEM/MASS,CUM,FY,,BRA/REL,EXP) +REACTION (94-PU-242(G,F)ELEM/MASS,CUM,FY,,BRA) ENDBIB 1 COMMON 1 3 -EN +EN-MAX MEV 20.7 ENDCOMMON 3 DATA 6 23 -MASS ELEMENT ELEMENT ISOMER DATA ERR-S -NO-DIM NO-DIM NO-DIM NO-DIM ARB-UNITS ARB-UNITS +MASS ELEMENT ELEMENT ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM NO-DIM PRD/FIS PRD/FIS 85. 36. 1. 0.82E-2 0.05E-2 87. 36. 1.35E-2 0.09E-2 88. 36. 37. 1.53E-2 0.28E-2 diff --git a/exforall/M02/M0295.x4 b/exforall/M02/M0295.x4 index a1afe1588..2ab9e10e2 100644 --- a/exforall/M02/M0295.x4 +++ b/exforall/M02/M0295.x4 @@ -1,32 +1,39 @@ -ENTRY M0295 910206 20050926 0000 -SUBENT M0295001 910206 20050926 0000 -BIB 11 20 -TITLE THE ACCUMULATION OF THE RADIONUCLIDE AT THE PHOTO- - AND ELECTRODISINTEGRATION OF NUCLEI IN THE REGION - NEAR TO A=90. -AUTHOR (V.G.BATIY,YU.V.VLADIMIROV,YU.N.RAKIVNENKO,YU.N.RANYUK, - O.A.RASTREPIN,E.A.SKAKUN) -INSTITUTE (4CCPKFT) -REFERENCE (J,AE,63,386,87) +ENTRY M0295 20110531 20111003 20110921 M059 +SUBENT M0295001 20110531 20111003 20110921 M059 +BIB 12 27 +TITLE The accumulation of the radionuclides at the photo- + and electrodisintegration of nuclei in the region + near to A = 90. +AUTHOR (V.G.Batiy,Yu.V.Vladimirov,Yu.N.Rakivnenko, + Yu.N.Ranyuk,O.A.Rastrepin,E.A.Skakun) +INSTITUTE (4UKRKFT) +FACILITY (LINAC,4UKRKFT) +REFERENCE (J,AE,63,386,1987) + (J,SJA,63,899,1987) + English translation of AE,63,386,1987. METHOD (ACTIV) PART-DET (FF) DETECTOR (GELI) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ARE -COMMENT THE RADIONUCLIDE YIELDS WERE INVESTIGATED BOMBARDING - Y, ZR, NB AND MO BY MEANS OF ELECTRONS AND - BREMSSTRAHLUNG GAMMA-QUANTA.THE THEORETICAL ANALYSIS - OF THE OBTAINED DATA WAS PERFORMED. THE AGREEMENT - BETWEEN EXPERIMENTAL DATA AND THEORETICAL CALCULATIONS - IS OBSERVED. -STATUS (TABLE). DATA ARE PUBLISHED IN FORM OF TABLES. -HISTORY (880803C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 20 +ERR-ANALYS (DATA-ERR) No information. +COMMENT The radionuclide yields were investigated bombarding + Y, Zr, Nb and Mo by beams of electrons and + bremsstrahlung gamma-quanta. The theoretical + analysis of the obtained data was performed. The + agreement between experimental data and theoretical + calculations was observed. +STATUS (TABLE) Data from Tables 1 and 2. +HISTORY (19880803C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: REFERENCE, + TITLE, INSTITUTE, FACILITY, REACTION in SUBENTs 003, + 005 and 007, dates, lowercase, additional data from + Table 2 for SUBENTS 008 - 015. +ENDBIB 27 NOCOMMON 0 0 -ENDSUBENT 23 -SUBENT M0295002 910206 20050926 0000 +ENDSUBENT 30 +SUBENT M0295002 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (42-MO-0(G,F)ELEM/MASS,,SIG,,BRA,EXP) +REACTION (42-MO-0(G,F)ELEM/MASS,,SIG,,BRA) INC-SOURCE (BRST) ENDBIB 2 COMMON 1 3 @@ -35,21 +42,21 @@ MEV 150. ENDCOMMON 3 DATA 5 8 -MASS ELEMENT ISOMER DATA ERR-S +ELEMENT MASS ISOMER DATA DATA-ERR NO-DIM NO-DIM NO-DIM MB MB - 87. 39. 0. 0.06 0.053 - 87. 39. 1. 0.34 0.05 - 89. 40. 1.18 0.18 - 90. 41. 1.14 0.31 - 90. 42. 0.51 0.10 - 93. 42. 1. 0.023 0.0014 - 96. 41. 0.81 0.15 - 99. 42. 6.5 1.7 + 39. 87. 0. 0.06 0.053 + 39. 87. 1. 0.34 0.05 + 40. 89. 1.18 0.18 + 41. 90. 1.14 0.31 + 41. 96. 0.81 0.15 + 42. 90. 0.51 0.1 + 42. 93. 1. 0.023 0.0014 + 42. 99. 6.5 1.7 ENDDATA 10 ENDSUBENT 21 -SUBENT M0295003 910206 20050926 0000 +SUBENT M0295003 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (42-MO-0(E,F)ELEM/MASS,,SIG,,BRA,EXP) +REACTION (42-MO-0(E,F)ELEM/MASS,,SIG) ENDBIB 1 COMMON 1 3 EN @@ -57,21 +64,21 @@ MEV 150. ENDCOMMON 3 DATA 5 8 -MASS ELEMENT ISOMER DATA ERR-S +ELEMENT MASS ISOMER DATA DATA-ERR NO-DIM NO-DIM NO-DIM MB MB - 87. 39. 0. 0.0031 0.0007 - 87. 39. 1. 0.0064 0.0005 - 89. 40. 0.0254 0.0019 - 90. 41. 0.031 0.004 - 90. 42. 0.0136 0.0012 - 93. 42. 1. 0.0012 0.00013 - 96. 41. 0.0221 0.0018 - 99. 42. 0.16 0.02 + 39. 87. 0. 0.0031 0.0007 + 39. 87. 1. 0.0064 0.0005 + 40. 89. 0.0254 0.0019 + 41. 90. 0.031 0.004 + 41. 96. 0.0221 0.0018 + 42. 90. 0.0136 0.0012 + 42. 93. 1. 0.0012 0.00013 + 42. 99. 0.16 0.02 ENDDATA 10 ENDSUBENT 20 -SUBENT M0295004 910206 20050926 0000 +SUBENT M0295004 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (42-MO-0(G,F)ELEM/MASS,,SIG,,BRA,EXP) +REACTION (42-MO-0(G,F)ELEM/MASS,,SIG,,BRA) INC-SOURCE (BRST) ENDBIB 2 COMMON 1 3 @@ -80,83 +87,272 @@ MEV 200. ENDCOMMON 3 DATA 5 8 -MASS ELEMENT ISOMER DATA ERR-S +ELEMENT MASS ISOMER DATA DATA-ERR NO-DIM NO-DIM NO-DIM MB MB - 87. 39. 0. 0.11 0.01 - 87. 39. 1. 0.55 0.08 - 89. 40. 1.57 0.24 - 90. 41. 1.6 0.4 - 90. 42. 0.51 0.10 - 93. 42. 1. 0.067 0.024 - 96. 41. 0.83 0.18 - 99. 42. 6.3 1.7 + 39. 87. 0. 0.11 0.01 + 39. 87. 1. 0.55 0.08 + 40. 89. 1.57 0.24 + 41. 90. 1.6 0.4 + 41. 96. 0.83 0.18 + 42. 90. 0.51 0.1 + 42. 93. 1. 0.067 0.024 + 42. 99. 6.3 1.7 ENDDATA 10 ENDSUBENT 21 -SUBENT M0295005 910206 20050926 0000 +SUBENT M0295005 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (42-MO-0(E,F)ELEM/MASS,,SIG,,BRA,EXP) +REACTION (42-MO-0(E,F)ELEM/MASS,,SIG) ENDBIB 1 COMMON 1 3 EN MEV - 150. + 200. ENDCOMMON 3 DATA 5 8 -MASS ELEMENT ISOMER DATA ERR-S +ELEMENT MASS ISOMER DATA DATA-ERR NO-DIM NO-DIM NO-DIM MB MB - 87. 39. 0. 0.0056 0.0013 - 87. 39. 1. 0.012 0.001 - 89. 40. 0.035 0.003 - 90. 41. 0.037 0.005 - 90. 42. 0.015 0.0013 - 93. 42. 1. 0.0011 0.0003 - 96. 41. 0.030 0.002 - 99. 42. 0.17 0.02 + 39. 87. 0. 0.0056 0.0013 + 39. 87. 1. 0.012 0.001 + 40. 89. 0.035 0.003 + 41. 90. 0.037 0.005 + 41. 96. 0.03 0.002 + 42. 90. 0.015 0.0013 + 42. 93. 1. 0.0011 0.0003 + 42. 99. 0.17 0.02 ENDDATA 10 ENDSUBENT 20 -SUBENT M0295006 910206 20050926 0000 +SUBENT M0295006 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (42-MO-0(G,F)ELEM/MASS,,SIG,,BRA,EXP) +REACTION (42-MO-0(G,F)ELEM/MASS,,SIG,,BRA) INC-SOURCE (BRST) ENDBIB 2 COMMON 1 3 EN-MAX MEV - 250. + 225. ENDCOMMON 3 DATA 5 8 -MASS ELEMENT ISOMER DATA ERR-S +ELEMENT MASS ISOMER DATA DATA-ERR NO-DIM NO-DIM NO-DIM MB MB - 87. 39. 0. 0.19 0.1 - 87. 39. 1. 0.53 0.09 - 89. 40. 1.2 0.2 - 90. 41. 1.3 0.3 - 90. 42. 0.42 0.01 - 93. 42. 1. 0.015 0.019 - 96. 41. 0.83 0.18 - 99. 42. 6.4 1.7 + 39. 87. 0. 0.19 0.1 + 39. 87. 1. 0.53 0.09 + 40. 89. 1.2 0.2 + 41. 90. 1.3 0.3 + 41. 96. 0.83 0.18 + 42. 90. 0.42 0.01 + 42. 93. 1. 0.015 0.019 + 42. 99. 6.4 1.7 ENDDATA 10 ENDSUBENT 21 -SUBENT M0295007 910206 20050926 0000 +SUBENT M0295007 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (42-MO-0(E,F)ELEM/MASS,,SIG,,BRA,EXP) +REACTION (42-MO-0(E,F)ELEM/MASS,,SIG) ENDBIB 1 COMMON 1 3 EN MEV - 250. + 225. ENDCOMMON 3 DATA 5 8 -MASS ELEMENT ISOMER DATA ERR-S +ELEMENT MASS ISOMER DATA DATA-ERR NO-DIM NO-DIM NO-DIM MB MB - 87. 39. 0. 0.0054 0.0014 - 87. 39. 1. 0.0143 0.0012 - 89. 40. 0.040 0.003 - 90. 41. 0.041 0.004 - 90. 42. 0.0153 0.0013 - 93. 42. 1. 0.0013 0.0002 - 96. 41. 0.027 0.003 - 99. 42. 0.21 0.02 + 39. 87. 0. 0.0054 0.0014 + 39. 87. 1. 0.0143 0.0012 + 40. 89. 0.04 0.003 + 41. 90. 0.041 0.004 + 41. 96. 0.027 0.003 + 42. 90. 0.0153 0.0013 + 42. 93. 1. 0.0013 0.0002 + 42. 99. 0.21 0.02 ENDDATA 10 ENDSUBENT 20 -ENDENTRY 7 +SUBENT M0295008 20110531 20111003 20110921 M059 +BIB 2 2 +REACTION (39-Y-89(G,F)ELEM/MASS,,SIG,,BRA) +INC-SOURCE (BRST) +ENDBIB 2 +COMMON 1 3 +EN-MAX +MEV + 275. +ENDCOMMON 3 +DATA 5 9 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM MB MB + 36. 77. 0.048 0.006 + 37. 81. 0. 2.2 0.4 + 38. 83. 0.54 0.09 + 39. 84. 0.17 0.02 + 39. 86. 0. 1.29 0.19 + 39. 86. 1. 0.41 0.05 + 39. 87. 0. 4.7 1.1 + 39. 87. 1. 3.3 0.4 + 39. 88. 75.0 8.0 +ENDDATA 11 +ENDSUBENT 22 +SUBENT M0295009 20110531 20111003 20110921 M059 +BIB 1 1 +REACTION (39-Y-89(E,F)ELEM/MASS,,SIG) +ENDBIB 1 +COMMON 1 3 +EN +MEV + 275. +ENDCOMMON 3 +DATA 5 9 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM MB MB + 36. 77. 0.00139 0.00014 + 37. 81. 0. 0.033 0.006 + 38. 83. 0.0121 0.0017 + 39. 84. 0.0040 0.0005 + 39. 86. 0. 0.043 0.004 + 39. 86. 1. 0.0143 0.0011 + 39. 87. 0. 0.16 0.02 + 39. 87. 1. 0.12 0.01 + 39. 88. 2.30 0.16 +ENDDATA 11 +ENDSUBENT 21 +SUBENT M0295010 20110531 20111003 20110921 M059 +BIB 1 1 +REACTION (40-ZR-0(G,F)ELEM/MASS,,SIG) +ENDBIB 1 +COMMON 1 3 +EN +MEV + 275. +ENDCOMMON 3 +DATA 5 5 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM MB MB + 39. 86. 1.6 0.3 + 39. 87. 0. 2.5 0.3 + 39. 87. 1. 0.25 0.006 + 40. 86. 1.23 0.51 + 40. 89. 1.33 0.10 +ENDDATA 7 +ENDSUBENT 17 +SUBENT M0295011 20110531 20111003 20110921 M059 +BIB 1 1 +REACTION (40-ZR-0(E,F)ELEM/MASS,,SIG) +ENDBIB 1 +COMMON 1 3 +EN +MEV + 275. +ENDCOMMON 3 +DATA 5 5 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM MB MB + 39. 86. 0.027 0.006 + 39. 87. 0. 0.031 0.010 + 39. 87. 1. 0.073 0.006 + 40. 86. 0.0111 0.0013 + 40. 89. 1.33 0.10 +ENDDATA 7 +ENDSUBENT 17 +SUBENT M0295012 20110531 20111003 20110921 M059 +BIB 2 2 +REACTION (41-NB-93(G,F)ELEM/MASS,,SIG,,BRA) +INC-SOURCE (BRST) +ENDBIB 2 +COMMON 1 3 +EN-MAX +MEV + 275. +ENDCOMMON 3 +DATA 5 12 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM MB MB + 37. 81. 0. 0.36 0.05 + 39. 84. 0.21 0.03 + 39. 86. 0. 1.04 0.12 + 39. 86. 1. 0.48 0.06 + 39. 87. 0. 0.56 0.21 + 39. 87. 1. 1.8 0.19 + 39. 90. 1. 0.063 0.001 + 40. 86. 0.23 0.03 + 40. 89. 3.6 0.5 + 41. 89. 0.28 0.04 + 41. 90. 3.21 0.46 + 41. 92. 1. 39.4 4.8 +ENDDATA 14 +ENDSUBENT 25 +SUBENT M0295013 20110531 20111003 20110921 M059 +BIB 1 1 +REACTION (41-NB-93(E,F)ELEM/MASS,,SIG) +ENDBIB 1 +COMMON 1 3 +EN +MEV + 275. +ENDCOMMON 3 +DATA 5 12 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM MB MB + 37. 81. 0. 0.0053 0.0007 + 39. 84. 0.0049 0.0005 + 39. 86. 0. 0.0170 0.0017 + 39. 86. 1. 0.011 0.001 + 39. 87. 0. 0.011 0.006 + 39. 87. 1. 0.033 0.003 + 39. 90. 1. 0.0019 0.0002 + 40. 86. 0.0066 0.0010 + 40. 89. 0.123 0.011 + 41. 89. 0.0057 0.0005 + 41. 90. 0.120 0.010 + 41. 92. 1. 1.10 0.09 +ENDDATA 14 +ENDSUBENT 24 +SUBENT M0295014 20110531 20111003 20110921 M059 +BIB 2 2 +REACTION (42-MO-0(G,F)ELEM/MASS,,SIG,,BRA) +INC-SOURCE (BRST) +ENDBIB 2 +COMMON 1 3 +EN-MAX +MEV + 275. +ENDCOMMON 3 +DATA 5 11 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM MB MB + 39. 86. 0.24 0.08 + 39. 87. 1. 0.80 0.08 + 39. 91. 1. 0.047 0.008 + 40. 86. 0.24 0.03 + 40. 89. 1.7 0.2 + 41. 89. 0.19 0.03 + 41. 90. 1.62 0.23 + 41. 90. 0.7 0.1 + 41. 96. 1.0 0.15 + 41. 97. 1.30 0.17 + 41. 99. 1. 6.5 1.2 +ENDDATA 13 +ENDSUBENT 24 +SUBENT M0295015 20110531 20111003 20110921 M059 +BIB 1 1 +REACTION (42-MO-0(E,F)ELEM/MASS,,SIG) +ENDBIB 1 +COMMON 1 3 +EN +MEV + 275. +ENDCOMMON 3 +DATA 5 11 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM MB MB + 39. 86. 0.0087 0.0017 + 39. 87. 1. 0.0154 0.0013 + 39. 91. 1. 0.001 0.0002 + 40. 86. 0.0053 0.0006 + 40. 89. 0.049 0.005 + 41. 89. 0.0064 0.0006 + 41. 90. 0.051 0.004 + 41. 90. 0.024 0.002 + 41. 96. 0.029 0.003 + 41. 97. 0.044 0.004 + 41. 99. 1. 0.20 0.03 +ENDDATA 13 +ENDSUBENT 23 +ENDENTRY 15 diff --git a/exforall/M02/M0296.x4 b/exforall/M02/M0296.x4 index aec12649e..dee25b270 100644 --- a/exforall/M02/M0296.x4 +++ b/exforall/M02/M0296.x4 @@ -1,55 +1,60 @@ -ENTRY M0296 20010201 20010711 20050926 0000 -SUBENT M0296001 20010201 20010711 20050926 0000 -BIB 11 17 -TITLE THE RATIO OF THE PHOTONEUTRON YIELDS ON THE ZR-90 - NUCLEI. -AUTHOR (M.G.DAVYDOV,I.B.RAKHMANOV,F.SH.KHAMRAEV) +ENTRY M0296 20110531 20111003 20110921 M059 +SUBENT M0296001 20110531 20111003 20110921 M059 +BIB 12 22 +TITLE The ratio of the photoneutron yields on the Zr-90 + nuclei. +AUTHOR (M.G.Davydov,I.B.Rakhmanov,F.Sh.Khamraev) INSTITUTE (4RUSRGU) REFERENCE (J,AE,63,362,1987) + (J,SJA,63,876,1987) + English translation of AE,63,362,1987. +FACILITY (BETAT,4RUSRGU) INC-SOURCE (BRST) METHOD (ACTIV) DETECTOR (GELI) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ARE PRESENTED. -COMMENT THE PHOTONEUTRON ISOMERIC YIELDS RATIO ON THE ZR-90 - WAS MEASURED IN THE RANGE OF THE END-POINT ENERGY OF - BREMSSTRAHLUNG BEAMS FROM 21.5 UP TO 24.5 MEV. -STATUS (CURVE) +ERR-ANALYS (ERR-S) Statistical errors are presented. +COMMENT The photoneutron isomeric yields ratio on the Zr-90 + was measured in the range of the end-point energy of + bremsstrahlung beams from 21.5 up to 24.5 MeV. +STATUS (TABLE) Data from Table. HISTORY (19880811C) - (19910202A) CORRECTED BY V.VARLAMOV, V.MCLANE. - (20010201A) CORRECTED BY V.VARLAMOV: DATAS (TWO TO - FOUR DIGITS) AND TITLE CORRECTED. -ENDBIB 17 + (19910202A) Corrected by V.Varlamov, V.McLane. + (20010201A) Corrected by V.Varlamov: DATAS (two to + four digits) and title corrected. + (20110531A) Corrected by V.Varlamov: REFERENCE, + FACILITY, lowercase. +ENDBIB 22 NOCOMMON 0 0 -ENDSUBENT 20 -SUBENT M0296002 20010201 20010711 20050926 0000 +ENDSUBENT 25 +SUBENT M0296002 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (40-ZR-90(G,N)40-ZR-89-M/G,,SIG/RAT,,BRA,EXP) +REACTION (40-ZR-90(G,N)40-ZR-89-M/G,,SIG/RAT,,BRA) ENDBIB 1 NOCOMMON 0 0 DATA 3 7 EN-MAX DATA ERR-S MEV NO-DIM NO-DIM 21.5 1.25 0.07 - 22.0 1.15 0.04 + 22. 1.15 0.04 22.5 1.18 0.04 - 23.0 1.21 0.04 + 23. 1.21 0.04 23.5 1.28 0.05 - 24.0 1.30 0.05 - 24.5 1.40 0.06 + 24. 1.3 0.05 + 24.5 1.4 0.06 ENDDATA 9 ENDSUBENT 15 -SUBENT M0296003 20010201 20010711 20050926 0000 +SUBENT M0296003 20110531 20111003 20110921 M059 BIB 1 2 -REACTION ((40-ZR-90(G,N)40-ZR-89,,SIG,,BRA,EXP)/ - (40-ZR-90(G,2N)40-ZR-88,,SIG,,BRA,EXP)) +REACTION ((40-ZR-90(G,N)40-ZR-89,,SIG,,BRA)/ + (40-ZR-90(G,2N)40-ZR-88,,SIG,,BRA)) ENDBIB 2 NOCOMMON 0 0 DATA 3 4 EN-MAX DATA ERR-S MEV NO-DIM NO-DIM - 23.0 170. 3. + 23. 170. 3. 23.5 134. 4. - 24.0 99. 1. + 24. 99. 1. 24.5 76. 2. ENDDATA 6 ENDSUBENT 13 diff --git a/exforall/M02/M0297.x4 b/exforall/M02/M0297.x4 index fddd80c8d..096c83c2a 100644 --- a/exforall/M02/M0297.x4 +++ b/exforall/M02/M0297.x4 @@ -1,96 +1,110 @@ -ENTRY M0297 910206 20050926 0000 -SUBENT M0297001 910206 20050926 0000 -BIB 11 16 -TITLE CROSS SECTIONS OF THE RB-85(G,N)RB-84-M,G REACTION. -AUTHOR (M.G.DAVYDOV,F.SH.KHAMRAEV,M.SHOMURODOV) -INSTITUTE (4CCPRGU) -REFERENCE (J,AE,62,193,87) +ENTRY M0297 20110531 20111003 20110921 M059 +SUBENT M0297001 20110531 20111003 20110921 M059 +BIB 10 20 +TITLE Cross sections of the Rb-85(g,n)Rb-84-m,g reaction. +AUTHOR (M.G.Davydov,F.Sh.Khamraev,M.Shomurodov) +INSTITUTE (4RUSRGU) +FACILITY (BETAT,4RUSRGU) 22 MeV. +REFERENCE (J,AE,62,193,1987) + (J,SJA,62,243,1987) + English translation of AE,62,193,1987. INC-SOURCE (BRST) METHOD (ACTIV) DETECTOR (GELI) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ARE PRESENTED. -COMMENT THE CROSS SECTIONS OF THE CREATION OF ISOMERIC STATES - RB-81-M,G IN PHOTONEUTRON REACTION ON RB-85 NUCLEUS - WERE MEASURED BY MEANS OF ACTIVATION METHOD. THE ENER- - GETICAL DEPENDENCES OF THE ISOMERIC YIELD RATIOS WERE - MEASURED UP TO 25 MEV WITH THE STEP 0.5 MEV. -STATUS (CURVE) -HISTORY (880811C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 16 +COMMENT The cross sections of the creation of isomeric states + Rb-81-m,g in photoneutron reaction on Rb-85 nucleus + were measured by means of activation method. The + energy dependences of the isomeric yield ratios were + measured up to 25 MeV with the step 0.5 MeV. +HISTORY (19880811C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: REFERENCE, + FACILITY, BRA -> BRS in SUBENTS 002 - 004, BRS -> + BRA in SUBENTS 005, 006, dates, lowercase. +ENDBIB 20 NOCOMMON 0 0 -ENDSUBENT 19 -SUBENT M0297002 910206 20050926 0000 -BIB 1 2 -REACTION (37-RB-85(G,N)37-RB-84,,SIG,,BRA,EXP) - TOTAL WIDTH = 4.7(0.3) MEV -ENDBIB 2 +ENDSUBENT 23 +SUBENT M0297002 20110531 20111003 20110921 M059 +BIB 3 4 +REACTION (37-RB-85(G,N)37-RB-84,,SIG,,BRS) + Total width = 4.7(0.3) MeV +ERR-ANALYS (ERR-S) Statistical errors are presented. +STATUS (TABLE) Data from Table 1. +ENDBIB 4 NOCOMMON 0 0 DATA 4 1 EN EN-ERR DATA ERR-S MEV MEV MB MB - 18.0 0.3 162. 16. + 18. 0.3 162. 16. ENDDATA 3 -ENDSUBENT 10 -SUBENT M0297003 910206 20050926 0000 -BIB 1 2 -REACTION (37-RB-85(G,N)37-RB-84-M,,SIG,,BRA,EXP) - TOTAL WIDTH = 4.2(0.3) MEV -ENDBIB 2 +ENDSUBENT 12 +SUBENT M0297003 20110531 20111003 20110921 M059 +BIB 3 4 +REACTION (37-RB-85(G,N)37-RB-84-M,,SIG,,BRS) + Total width = 4.2(0.3) MeV +ERR-ANALYS (ERR-S) Statistical errors are presented. +STATUS (TABLE) Data from Table 1. +ENDBIB 4 NOCOMMON 0 0 DATA 4 1 EN EN-ERR DATA ERR-S MEV MEV MB MB - 18.0 0.3 40. 5. + 18. 0.3 40. 5. ENDDATA 3 -ENDSUBENT 10 -SUBENT M0297004 910206 20050926 0000 -BIB 1 2 -REACTION (37-RB-85(G,N)37-RB-84-G,,SIG,,BRA,EXP) - TOTAL WIDTH = 5.0(0.3) MEV -ENDBIB 2 +ENDSUBENT 12 +SUBENT M0297004 20110531 20111003 20110921 M059 +BIB 3 4 +REACTION (37-RB-85(G,N)37-RB-84-G,,SIG,,BRS) + Total width = 5.0(0.3) MeV +ERR-ANALYS (ERR-S) Statistical errors are presented. +STATUS (TABLE) Data from Table 1. +ENDBIB 4 NOCOMMON 0 0 DATA 4 1 EN EN-ERR DATA ERR-S MEV MEV MB MB - 18.0 0.3 122. 15. + 18. 0.3 122. 15. ENDDATA 3 -ENDSUBENT 10 -SUBENT M0297005 910206 20050926 0000 -BIB 1 3 -REACTION 1(37-RB-85(G,N)37-RB-84,,INT,,BRS,EXP) - 2(37-RB-85(G,N)37-RB-84-M,,INT,,BRS,EXP) - 3(37-RB-85(G,N)37-RB-84-G,,INT,,BRS,EXP) -ENDBIB 3 +ENDSUBENT 12 +SUBENT M0297005 20110531 20111003 20110921 M059 +BIB 3 5 +REACTION 1(37-RB-85(G,N)37-RB-84,,INT,,BRA) + 2(37-RB-85(G,N)37-RB-84-M,,INT,,BRA) + 3(37-RB-85(G,N)37-RB-84-G,,INT,,BRA) +ERR-ANALYS No information. +STATUS (TABLE) Data from Table 1. +ENDBIB 5 NOCOMMON 0 0 DATA 4 1 EN-MAX DATA 1DATA 2DATA 3 MEV MB*MEV MB*MEV MB*MEV - 25.0 871. 175. 602. + 25. 871. 175. 602. ENDDATA 3 -ENDSUBENT 11 -SUBENT M0297006 910206 20050926 0000 -BIB 1 1 -REACTION (37-RB-85(G,N)37-RB-84-M/G,,SIG/RAT,,BRS,EXP) -ENDBIB 1 +ENDSUBENT 13 +SUBENT M0297006 20110531 20111003 20110921 M059 +BIB 3 3 +REACTION (37-RB-85(G,N)37-RB-84-M/G,,SIG/RAT,,BRA) +ERR-ANALYS (ERR-S) Statistical errors are presented. +STATUS (CURVE) Data from Figure. +ENDBIB 3 NOCOMMON 0 0 DATA 3 14 EN-MAX DATA ERR-S MEV NO-DIM NO-DIM -12. 0.090 0.020 -13. 0.135 0.020 -14. 0.180 0.020 -15. 0.200 0.020 -16. 0.273 0.020 -17. 0.290 0.020 -18. 0.285 0.020 -19. 0.325 0.020 -20. 0.315 0.020 -21. 0.313 0.020 -22. 0.343 0.010 -23. 0.330 0.010 -24. 0.342 0.010 -25. 0.341 0.010 +12. 0.09 0.02 +13. 0.135 0.02 +14. 0.18 0.02 +15. 0.2 0.02 +16. 0.273 0.02 +17. 0.290 0.02 +18. 0.285 0.02 +19. 0.325 0.02 +20. 0.315 0.02 +21. 0.313 0.02 +22. 0.343 0.01 +23. 0.33 0.01 +24. 0.342 0.01 +25. 0.341 0.01 ENDDATA 16 -ENDSUBENT 22 +ENDSUBENT 24 ENDENTRY 6 diff --git a/exforall/M02/M0298.x4 b/exforall/M02/M0298.x4 index 42a157336..3f56ec9be 100644 --- a/exforall/M02/M0298.x4 +++ b/exforall/M02/M0298.x4 @@ -1,28 +1,40 @@ -ENTRY M0298 910206 20050926 0000 -SUBENT M0298001 910206 20050926 0000 -BIB 11 15 -TITLE THE YIELDS AND CROSS SECTIONS OF COBALT - PHOTOACTIVATION. -AUTHOR (M.G.DAVYDOV,F.SH.KHAMRAEV,E.M.SHOMURODOV) -INSTITUTE (4CCPRGU) -REFERENCE (J,AE,63,44,87) +ENTRY M0298 20110531 20111003 20110921 M059 +SUBENT M0298001 20110531 20111003 20110921 M059 +BIB 12 26 +TITLE The yields and cross sections of cobalt + photoactivation. +AUTHOR (M.G.Davydov,F.Sh.Khamraev,E.M.Shomurodov) +INSTITUTE (4RUSRGU) +REFERENCE (J,AE,63,44,1987) + (J,SJA,63,545,1987) + English translation of AE,63,44,1987. +FACILITY (BETAT,4RUSRGU) INC-SOURCE (BRST) METHOD (ACTIV) DETECTOR (GELI) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ARE PRESENTED. -COMMENT THE ISOMERIC YIELDS RATIO IH THE CO-59(Y,N)CO-58-M,G - REACTION AND ABSOLUTE CROSS SECTIONS OF PHOTOACTIVATION - OF ISOMERIC STATES WERE MEASURED IN DGR REGION. -STATUS (CURVE) -HISTORY (880811C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 15 +COMMENT The isomeric yields ratio in the Co-59(g,n)Co-58-m,g + reaction and absolute cross sections of + photoactivation of isomeric states were measured in + GDR region. +CRITIQUE There are several mistakes both in text and Table 2 + for data headings and units, for example, for cross + section amplitude SIGMA-m unit mb*MeV is presented, + integrated cross section SIGMA-int(E) is presented + as SIGMA-int (E), mb(MeV). +STATUS (TABLE) Data from Tables 1 and 2. +HISTORY (19880811C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: REFERENCE, + INSTUTUTE, FACILITY, BRS -> BRA in SUBENT 002, + SUBENTS 003 - 005 recompiled, dates, lowercase. +ENDBIB 26 NOCOMMON 0 0 -ENDSUBENT 18 -SUBENT M0298002 910206 20050926 0000 -BIB 1 1 -REACTION (27-CO-59(G,N)27-CO-58-M/G,,SIG/RAT,,BRS,EXP) -ENDBIB 1 +ENDSUBENT 29 +SUBENT M0298002 20110531 20111003 20110921 M059 +BIB 2 2 +REACTION (27-CO-59(G,N)27-CO-58-M/G,,SIG/RAT,,BRA) +ERR-ANALYS (ERR-S) Statistical errors are presented. +ENDBIB 2 NOCOMMON 0 0 DATA 3 13 EN-MAX DATA ERR-S @@ -36,49 +48,85 @@ MEV NO-DIM NO-DIM 19. 1.24 0.02 20. 1.17 0.02 21. 1.28 0.02 - 22. 1.20 0.01 - 23. 1.20 0.01 + 22. 1.2 0.01 + 23. 1.2 0.01 24. 1.21 0.01 25. 1.19 0.01 ENDDATA 15 -ENDSUBENT 21 -SUBENT M0298003 910206 20050926 0000 -BIB 1 3 -REACTION 1(27-CO-59(G,N)27-CO-58-M,,SIG,,BRA,EXP) - TOTAL WIDTH = 4.5 MEV - 2(27-CO-59(G,N)27-CO-58-M,,INT,,BRA,EXP) +ENDSUBENT 22 +SUBENT M0298003 20110531 20111003 20110921 M059 +BIB 2 3 +REACTION (27-CO-59(G,N)27-CO-58-M,,SIG,,BRS) + Total width = 4.5 MeV +ERR-ANALYS No information. ENDBIB 3 NOCOMMON 0 0 -DATA 4 1 -EN DATA 1DATA 2ERR-S 2 -MEV MB MB*MEV MB*MEV - 17.1 40. 205. 25. +DATA 2 1 +EN DATA +MEV MB + 17.1 40. ENDDATA 3 ENDSUBENT 11 -SUBENT M0298004 910206 20050926 0000 -BIB 1 3 -REACTION 1(27-CO-59(G,N)27-CO-58-G,,SIG,,BRA,EXP) - TOTAL WIDTH = 4.0 MEV - 2(27-CO-59(G,N)27-CO-58-G,,INT,,BRA,EXP) +SUBENT M0298004 20110531 20111003 20110921 M059 +BIB 2 3 +REACTION (27-CO-59(G,N)27-CO-58-G,,SIG,,BRS) + Total width = 4.0 MeV +ERR-ANALYS No information. ENDBIB 3 NOCOMMON 0 0 -DATA 4 1 -EN DATA 1DATA 2ERR-S 2 -MEV MB MB*MEV MB*MEV - 17.0 32.5 152. 25. +DATA 2 1 +EN DATA +MEV MB + 17.0 32.5 ENDDATA 3 ENDSUBENT 11 -SUBENT M0298005 910206 20050926 0000 -BIB 1 3 -REACTION 1(27-CO-59(G,N)27-CO-58,,SIG,,BRA,EXP) - TOTAL WIDTH = 4.4 MEV - 2(27-CO-59(G,N)27-CO-58,,INT,,BRA,EXP) +SUBENT M0298005 20110531 20111003 20110921 M059 +BIB 2 3 +REACTION (27-CO-59(G,N)27-CO-58,,SIG,,BRS) + Total width = 4.4 MeV +ERR-ANALYS No information. ENDBIB 3 NOCOMMON 0 0 -DATA 4 1 -EN DATA 1DATA 2ERR-S 2 -MEV MB MB*MEV MB*MEV - 17.1 72.5 357. 25. +DATA 2 1 +EN DATA +MEV MB + 17.1 72.5 ENDDATA 3 ENDSUBENT 11 -ENDENTRY 5 +SUBENT M0298006 20110531 20111003 20110921 M059 +BIB 2 2 +REACTION (27-CO-59(G,N)27-CO-58-M,,INT,,BRA) +ERR-ANALYS No information. +ENDBIB 2 +NOCOMMON 0 0 +DATA 3 1 +EN-MIN EN-MAX DATA +MEV MEV MB*MEV + 0. 25. 205. +ENDDATA 3 +ENDSUBENT 10 +SUBENT M0298007 20110531 20111003 20110921 M059 +BIB 2 2 +REACTION (27-CO-59(G,N)27-CO-58-G,,INT,,BRA) +ERR-ANALYS No information. +ENDBIB 2 +NOCOMMON 0 0 +DATA 3 1 +EN-MIN EN-MAX DATA +MEV MEV MB*MEV + 0. 25. 152. +ENDDATA 3 +ENDSUBENT 10 +SUBENT M0298008 20110531 20111003 20110921 M059 +BIB 2 2 +REACTION (27-CO-59(G,N)27-CO-58,,INT,,BRA) +ERR-ANALYS No information. +ENDBIB 2 +NOCOMMON 0 0 +DATA 3 1 +EN-MIN EN-MAX DATA +MEV MEV MB*MEV + 0. 25. 357. +ENDDATA 3 +ENDSUBENT 10 +ENDENTRY 8 diff --git a/exforall/M02/M0299.x4 b/exforall/M02/M0299.x4 index 5069f4f43..82746c458 100644 --- a/exforall/M02/M0299.x4 +++ b/exforall/M02/M0299.x4 @@ -1,76 +1,63 @@ -ENTRY M0299 910206 20050926 0000 -SUBENT M0299001 910206 20050926 0000 -BIB 11 14 -TITLE THE ISOMERIC RATIO OF THE PHOTONUCLEAR REACTIONS - YIELDS (CROSS SECTIONS). -AUTHOR (M.G.DAVYDOV,V.G.MAGERA,A.V.TRUKHOV) -INSTITUTE (4CCPRGU) -REFERENCE (J,AE,62,236,87) +ENTRY M0299 20110531 20111003 20110921 M059 +SUBENT M0299001 20110531 20111003 20110921 M059 +BIB 12 21 +TITLE The isomeric ratio of the photonuclear reactions + yields (cross sections). +AUTHOR (M.G.Davydov,V.G.Magera,A.V.Trukhov) +INSTITUTE (4RUSRGU) +FACILITY (BETAT,4RUSRGU) +REFERENCE (J,AE,62,236,1987) + (J,SJA,62,277,1987) + English translation of AE,62,236,1987. INC-SOURCE (BRST) METHOD (ACTIV) DETECTOR (GELI) -ERR-ANALYS (ERR-S) STATISTICAL ERRORS ARE PRESENTED. -COMMENT THE ISOMERIC YIELDS FOR SOME PHOTONUCLEAR REACTIONS - WERE MEASURED BY ACTIVATION METHOD IN THE DGR REGION. +ERR-ANALYS (ERR-S) Statistical errors are presented. +COMMENT The isomeric yields for some photonuclear reactions + were measured by activation method in the GDR + region. STATUS (CURVE) -HISTORY (880811C) - (910202A) CORRECTED BY V.VARLAMOV, V.MCLANE -ENDBIB 14 +HISTORY (19880811C) + (19910202A) Corrected by V.Varlamov, V.McLane + (20110531A) Corrected by V.Varlamov: REFERENCE, + INSTITUTE, FACILITY, BRS -> BRA, lowercase, NODATA + because of 1 point in arb.units. +ENDBIB 21 NOCOMMON 0 0 -ENDSUBENT 17 -SUBENT M0299002 910206 20050926 0000 +ENDSUBENT 24 +SUBENT M0299002 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (32-GE-76(G,N)32-GE-75-M,,SIG,,BRS/REL,EXP) +REACTION (32-GE-76(G,N)32-GE-75-M,,SIG,,BRA/REL) ENDBIB 1 NOCOMMON 0 0 -DATA 3 1 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 22. 1.16 0.41 -ENDDATA 3 -ENDSUBENT 9 -SUBENT M0299003 910206 20050926 0000 +NODATA 0 0 +ENDSUBENT 5 +SUBENT M0299003 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (32-GE-76(G,N)32-GE-75-G,,SIG,,BRS/REL,EXP) +REACTION (32-GE-76(G,N)32-GE-75-G,,SIG,,BRA/REL) ENDBIB 1 NOCOMMON 0 0 -DATA 3 1 -EN-MIN DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 18. 0.33 0.04 -ENDDATA 3 -ENDSUBENT 9 -SUBENT M0299004 910206 20050926 0000 +NODATA 0 0 +ENDSUBENT 5 +SUBENT M0299004 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (42-MO-92(G,N)42-MO-91-G,,SIG,,BRS/REL,EXP) +REACTION (42-MO-92(G,N)42-MO-91-G,,SIG,,BRA/REL) ENDBIB 1 NOCOMMON 0 0 -DATA 3 1 -EN-MIN DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 18. 1.82 0.28 -ENDDATA 3 -ENDSUBENT 9 -SUBENT M0299005 910206 20050926 0000 +NODATA 0 0 +ENDSUBENT 5 +SUBENT M0299005 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (42-MO-98(G,P)41-NB-97-M,,SIG,,BRA/REL,EXP) +REACTION (42-MO-98(G,P)41-NB-97-M,,SIG,,BRA/REL) ENDBIB 1 NOCOMMON 0 0 -DATA 4 1 -EN-MIN EN-MAX DATA ERR-S -MEV MEV ARB-UNITS ARB-UNITS - 20. 25. 0.58 0.11 -ENDDATA 3 -ENDSUBENT 9 -SUBENT M0299006 910206 20050926 0000 +NODATA 0 0 +ENDSUBENT 5 +SUBENT M0299006 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (54-XE-136(G,N)54-XE-135,,SIG,,BRS/REL,EXP) +REACTION (54-XE-136(G,N)54-XE-135,,SIG,,BRA/REL) ENDBIB 1 NOCOMMON 0 0 -DATA 3 1 -EN-MAX DATA ERR-S -MEV ARB-UNITS ARB-UNITS - 22. 0.10 0.02 -ENDDATA 3 -ENDSUBENT 9 +NODATA 0 0 +ENDSUBENT 5 ENDENTRY 6 diff --git a/exforall/M04/M0479.x4 b/exforall/M04/M0479.x4 index 9907d298e..71bd02fc3 100644 --- a/exforall/M04/M0479.x4 +++ b/exforall/M04/M0479.x4 @@ -1,12 +1,12 @@ -ENTRY M0479 20110210 20110518 20110427 M057 -SUBENT M0479001 20110210 20110518 20110427 M057 -BIB 12 30 +ENTRY M0479 20110504 20111003 20110921 M059 +SUBENT M0479001 20110504 20111003 20110921 M059 +BIB 12 32 TITLE Cross sections of the reactions He-3(g,p)H-2 and He-3(g,n)2p. AUTHOR (A.N.Gorbunov,A.T.Varfolomeev) REFERENCE (J,PL,11,137,1964) - (J,JET,20,20,1965) English translation of ZET,47,30 (J,ZET,47,30,1964) + (J,JET,20,20,1965) English translation of ZET,47,30 INSTITUTE (4RUSLEB) FACILITY (SYNCH,4RUSLEB) METHOD (MAGFR,COINC) @@ -31,13 +31,15 @@ HISTORY (19910218C) (20110210A) Corrected by V.Varlamov: dates, CCP -> RUS, REFERENCE, ERR-S, DATA-ERR, ERR-SYS, BRA -> BRS, DATA-CM, DATA in SUBENT 006 re-digitized, lowercase. -ENDBIB 30 + (20110504A) Corrected by V.Varlamov: DATA in SUBENT + 006 redigitized. +ENDBIB 32 COMMON 1 3 ERR-SYS PER-CENT 6. ENDCOMMON 3 -ENDSUBENT 37 +ENDSUBENT 39 SUBENT M0479002 20110210 20110518 20110427 M057 BIB 4 12 REACTION (2-HE-3(G,P)1-H-2,,SIG) @@ -205,7 +207,7 @@ MEV MB MB 113. .11 .03 ENDDATA 23 ENDSUBENT 32 -SUBENT M0479006 20110210 20110518 20110427 M057 +SUBENT M0479006 20110504 20111003 20110921 M059 BIB 3 3 REACTION (2-HE-3(G,P)1-H-2,,DA,,BRA/REL) INC-SOURCE (BRST) @@ -219,18 +221,18 @@ ENDCOMMON 3 DATA 3 12 ANG-CM DATA-CM ERR-S ADEG ARB-UNITS ARB-UNITS - 10. .51 .51 - 20. 6.45 1.04 - 40. 14.59 1.52 - 50. 23.24 2.02 - 70. 22.79 1.97 - 80. 20.7 1.77 - 100. 19.34 1.89 - 110. 17.98 1.96 - 130. 9.56 1.39 - 140. 5.87 1.06 - 160. 3.32 .63 - 170. 2.27 1.14 + 7.5 .51 .51 + 22.5 6.45 1.04 + 37.5 14.59 1.52 + 52.5 23.24 2.02 + 67.5 22.79 1.97 + 82.5 20.7 1.77 + 97.5 19.34 1.89 + 112.5 17.98 1.96 + 127.5 9.56 1.39 + 142.5 5.87 1.06 + 157.5 3.32 .63 + 172.5 2.27 1.14 ENDDATA 14 ENDSUBENT 26 ENDENTRY 6 diff --git a/exforall/M05/M0529.x4 b/exforall/M05/M0529.x4 index 58325e857..d38484b8f 100644 --- a/exforall/M05/M0529.x4 +++ b/exforall/M05/M0529.x4 @@ -1,37 +1,41 @@ -ENTRY M0529 980319 20050926 0000 -SUBENT M0529001 980319 20050926 0000 -BIB 14 21 -TITLE RUBIDIUM ISOTOPES PHOTONEUTRON REACTION YIELD ISOMER - RATIOS. -AUTHOR (I.V.BODROV,M.G.DAVYDOV,A.R.MIKHELEV,E.E.PISHCHULINA, - A.V.TRUKHOV) +ENTRY M0529 20110531 20111003 20110921 M059 +SUBENT M0529001 20110531 20111003 20110921 M059 +BIB 14 25 +TITLE Rubidium isotopes photoneutron reaction yield isomer + ratios. +AUTHOR (I.V.Bodrov,M.G.Davydov,A.R.Mikhelev,E.E.Pishchulina, + A.V.Trukhov) INSTITUTE (4RUSRGU) -REFERENCE (J,AE,75,(1),75,93) +REFERENCE (J,AE,75,75,1993) + (J,AE/T,75,584,1993) + English translation of AE,75,75,1993. INC-SOURCE (BRST) FACILITY (BETAT,4RUSRGU) -SAMPLE THE SAMPLES OF NATURAL RUBIDIUM. -METHOD (ACTIV) INDUCED G-ACTIVITY WAS MEASURED. +SAMPLE The samples of natural rubidium. +METHOD (ACTIV) Induced g-activity was measured. DETECTOR (GELI) GE(LI)-DETECTOR. -ANALYSIS (AREA) ISOMER YIELD AND RATIO MEASUREMENT USING THE - G-QUANTA ENERGY SPECTRUM LINES DATA. -ERR-ANALYS (DATA-ERR) STATISTICAL ERRORS ARE GIVEN. -STATUS (TABLE) DATA WERE PREPARED IN THE MSU INP CDFE BY - V.V.VARLAMOV. -COMMENT IN ADDITION TO PREVIOUSLY PUBLISHED DATA FOR THE - REACTION RB-85(G,N)RB-84-G,M THE REACTIONS - RB-87(G,N)RB-86-G,M WERE INVESTIGATED USUNG THE - BREMSSTRAHLUNG G-QUANTA OF BETATRON. -HISTORY (980319C) -ENDBIB 21 -NOCOMMON -ENDSUBENT 24 -SUBENT M0529002 980319 20050926 0000 +ANALYSIS (AREA) Isomer yield and ratio measurement using the + g-quanta energy spectrum lines data. +ERR-ANALYS (ERR-S) Statistical errors are given. +STATUS (TABLE) Data from Table 2 were compiled at the + Russia MSU SINP CDFE by V.Varlamov. +COMMENT In addition to previously published data for the + reaction Rb-85(g,n)Rb-84-g,m the reactions + Rb-87(g,n)Rb-86-g,m were investigated using the + bremsstrahlung g-quanta of betatron. +HISTORY (19980319C) + (20110531A) Corrected by V.Varlamov: REFERENCE, + ERR-S, dates, lowercase, typos. +ENDBIB 25 +NOCOMMON 0 0 +ENDSUBENT 28 +SUBENT M0529002 20110531 20111003 20110921 M059 BIB 1 1 -REACTION (37-RB-87(G,N)37-RB-86-M/G,,SIG/RAT,,BRA,EXP) +REACTION (37-RB-87(G,N)37-RB-86-M/G,,SIG/RAT,,BRA) ENDBIB 1 -NOCOMMON +NOCOMMON 0 0 DATA 3 11 -EN-MAX DATA DATA-ERR +EN-MAX DATA ERR-S MEV NO-DIM NO-DIM 14. .064 .013 15. .053 .011 diff --git a/exforall/M05/M0539.x4 b/exforall/M05/M0539.x4 index ad31fceb8..8f5587478 100644 --- a/exforall/M05/M0539.x4 +++ b/exforall/M05/M0539.x4 @@ -1,52 +1,54 @@ -ENTRY M0539 20010504 20010711 20050926 0000 -SUBENT M0539001 20010504 20010711 20050926 0000 -BIB 14 30 -TITLE PHOTONEUTRON REACTIONS ON AL, S, TA, AND BI. -AUTHOR (G.P.ANTROPOV,I.E.MITROFANOV,B.S.RUSSKIKH) +ENTRY M0539 20110512 20111003 20110921 M059 +SUBENT M0539001 20110512 20111003 20110921 M059 +BIB 14 32 +TITLE Photoneutron reactions on Al, S, Ta, and Bi. +AUTHOR (G.P.Antropov,I.E.Mitrofanov,B.S.Russkikh) INSTITUTE (4RUSFTI) -REFERENCE (J,IZV,31,336,19670000) +REFERENCE (J,IZV,31,336,1967) + (J,BAS,31,320,1968) + English translation of IZV,31,336,1967. INC-SOURCE (BRST) FACILITY (BETAT,4RUSFTI) -SAMPLE NATURAL MIXTURE AL, S, TA, BI SAMPLES. -METHOD (EXTB,SITA) THE REACTION YIELD CURVE MEASUREMENT. +SAMPLE Natural mixture Al, S, Ta, Bi samples. +METHOD (EXTB,SITA) The reaction yield curve measurement. DETECTOR (BF3) -ANALYSIS (PLA) THE PENFOLD-LEISS METHOD FOR CROSS SECTION - UNFOLDING FROM THE YIELD CURVE. -CORRECTION ABOVE TWO-NEUTRON REACTION THRESHOLDS THE - REACTION (G,2N) CROSS SECTIONS WERE CALCULATED USING - THE WEISSKOPF'S FORMULAE ASSUMING A STATISTICAL - DECAY OF THE GDR STATES. -STATUS (CURVE) DATA WERE PREPARED IN THE MSU INP CDFE BY - V.V.VARLAMOV. -COMMENT THE TOTAL PHOTONEUTRON REACTION (G,XN) CROSS SECTIONS - WERE OBTAINED FOR NATURAL AL, S, TA, BI TARGETS FROM - THRESHOLDS TO 30 MEV BY DIRECTLY COUNTING OF - PHOTONEUTRONS AS A FUNCTIONS OF BREMSSTRAHLUNG - ENERGY. THE (G,2N) REACTION CROSS SECTIONS FOR TA - AND BI WERE CALCULATED USING THE STATISTICAL THEORY - OF THE GDR STATES DECAY AND USED TO OBTAIN THE - (G,SN) REACTION CROSS SECTIONS FOR THESE NUCLEI. - D.BLATT,V.WEISSKOPF. THEORETICAL NUCLEAR PHYSICS. - INOSTRANNAYA LITERATURA, MOSCOW, 1954. METHOD FOR THE - REACTION (G,2N) CROSS SECTION CALCULATION. +ANALYSIS (PLA) The Penfold-Leiss method for cross section + unfolding from the yield curve. +CORRECTION Above two-neutron reaction threshold the + reaction (g,2n) cross section was calculated using + the Weisskopf's formulae assuming a statistical + decay of the GDR states. +STATUS (CURVE) Data were compiled at the Russia MSU SINP + CDFE by V.Varlamov. +COMMENT The total photoneutron reaction (g,xn) cross sections + were obtained for natural Al, S, Ta, Bi targets from + thresholds to 30 MeV by directly counting of + photoneutrons as a functions of bremsstrahlung + energy. The (g,2n) reaction cross sections for Ta + and Bi were calculated using the statistical theory + of the GDR states decay and used to obtain the + (g,sn) reaction cross sections for these nuclei. HISTORY (19980915C) - (20010112A) CORRECTED BY V.VARLAMOV: TITLE CHANGED. -ENDBIB 30 + (20010112A) Corrected by V.Varlamov: title changed. + (20110512A) Corrected by V.Varlamov: REFERENCE, + COMMENT, ERR-ANALYS, DATA in SUBENTs 002 and 007 + substituted, lowercase. +ENDBIB 32 NOCOMMON 0 0 -ENDSUBENT 33 -SUBENT M0539002 20010504 20010711 20050926 0000 +ENDSUBENT 35 +SUBENT M0539002 20110512 20111003 20110921 M059 BIB 2 4 -REACTION (13-AL-27(G,X)0-NN-1,,SIG,,BRS,EXP) - THE SUM OF THE (G,N), (G,NP), AND 2(G,2N) REACTION - CROSS SECTIONS. -ERR-ANALYS (DATA-ERR) STATISTICAL ERRORS ARE GIVEN. +REACTION (13-AL-27(G,X)0-NN-1,,SIG,,BRS) + The sum of the (g,n), (g,np), and 2(g,2n) reaction + cross sections. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. ENDBIB 4 NOCOMMON 0 0 DATA 3 25 EN DATA DATA-ERR MEV MB MB 13.5 0.53 - 14. 11.62 + 14. 1.62 14.5 0.5 15. 0.4 15.5 0.81 @@ -72,12 +74,12 @@ MEV MB MB 25.5 1.84 0.78 ENDDATA 27 ENDSUBENT 36 -SUBENT M0539003 20010504 20010711 20050926 0000 +SUBENT M0539003 20110512 20111003 20110921 M059 BIB 2 4 -REACTION (16-S-0(G,X)0-NN-1,,SIG,,BRS,EXP) - THE SUM OF THE (G,N), (G,NP), AND 2(G,2N) REACTION - CROSS SECTIONS. -ERR-ANALYS (DATA-ERR) STATISTICAL ERRORS ARE GIVEN. +REACTION (16-S-0(G,X)0-NN-1,,SIG,,BRS) + The sum of the (g,n), (g,np), and 2(g,2n) reaction + cross sections. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. ENDBIB 4 NOCOMMON 0 0 DATA 3 25 @@ -110,12 +112,12 @@ MEV MB MB 25.5 1.49 1. ENDDATA 27 ENDSUBENT 36 -SUBENT M0539004 20010504 20010711 20050926 0000 +SUBENT M0539004 20110512 20111003 20110921 M059 BIB 2 4 -REACTION (73-TA-181(G,X)0-NN-1,,SIG,,BRS,EXP) - THE SUM OF THE (G,N), (G,NP), AND 2(G,2N) REACTION - CROSS SECTIONS. -ERR-ANALYS (DATA-ERR) STATISTICAL ERRORS ARE GIVEN. +REACTION (73-TA-181(G,X)0-NN-1,,SIG,,BRS) + The sum of the (g,n), (g,np), and 2(g,2n) reaction + cross sections. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. ENDBIB 4 NOCOMMON 0 0 DATA 3 25 @@ -148,12 +150,18 @@ MEV MB MB 20. 162.4 33. ENDDATA 27 ENDSUBENT 36 -SUBENT M0539005 20010504 20010711 20050926 0000 -BIB 1 3 -REACTION (73-TA-181(G,X)0-NN-1,UNW,SIG,,BRS,EXP) - THE SUM OF THE (G,N), (G,NP), AND (G,2N) REACTION - CROSS SECTIONS. -ENDBIB 3 +SUBENT M0539005 20110512 20111003 20110921 M059 +BIB 4 9 +REACTION (73-TA-181(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) + The sum of the (g,n), (g,np), and (g,2n) reaction + cross sections. +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0539004) +ERR-ANALYS No information. +ENDBIB 9 NOCOMMON 0 0 DATA 2 14 EN DATA @@ -173,12 +181,17 @@ MEV MB 19. 90.8 20. 69. ENDDATA 16 -ENDSUBENT 24 -SUBENT M0539006 20010504 20010711 20050926 0000 -BIB 2 2 -REACTION (73-TA-181(G,2N)73-TA-179,,SIG,,BRS,EXP) -ERR-ANALYS NO INFORMATION. -ENDBIB 2 +ENDSUBENT 30 +SUBENT M0539006 20110512 20111003 20110921 M059 +BIB 4 7 +REACTION (73-TA-181(G,2N)73-TA-179,,SIG,,BRS,DERIV) +ANALYSIS The (g,2n) reaction cross section was obtained + from the (g,xn) reaction cross section unfolded + from reaction yield measured using statistical + theory. +STATUS (DEP,M0539004) +ERR-ANALYS No information. +ENDBIB 7 NOCOMMON 0 0 DATA 2 7 EN DATA @@ -191,20 +204,20 @@ MEV MB 19. 97.2 19.5 77.8 ENDDATA 9 -ENDSUBENT 16 -SUBENT M0539007 20010504 20010711 20050926 0000 +ENDSUBENT 21 +SUBENT M0539007 20110512 20111003 20110921 M059 BIB 2 4 -REACTION (83-BI-209(G,X)0-NN-1,,SIG,,BRS,EXP) - THE SUM OF THE (G,N), (G,NP), AND 2(G,2N) REACTION - CROSS SECTIONS. -ERR-ANALYS NO INFORMATION. +REACTION (83-BI-209(G,X)0-NN-1,,SIG,,BRS) + The sum of the (g,n), (g,np), and 2(g,2n) reaction + cross sections. +ERR-ANALYS No information. ENDBIB 4 NOCOMMON 0 0 DATA 2 27 EN DATA MEV MB 7.5 20.5 - 8. 65.5 + 7.75 65.5 8. 40.9 8.5 66.9 9. 100.3 @@ -232,13 +245,18 @@ MEV MB 20. 109.2 ENDDATA 29 ENDSUBENT 38 -SUBENT M0539008 20010504 20010711 20050926 0000 -BIB 2 4 -REACTION (83-BI-209(G,X)0-NN-1,UNW,SIG,,BRS,EXP) - THE SUM OF THE (G,N), (G,NP), AND (G,2N) REACTION - CROSS SECTIONS. -ERR-ANALYS NO INFORMATION. -ENDBIB 4 +SUBENT M0539008 20110512 20111003 20110921 M059 +BIB 4 9 +REACTION (83-BI-209(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) + The sum of the (g,n), (g,np), and (g,2n) reaction + cross sections. +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0539007) +ERR-ANALYS No information. +ENDBIB 9 NOCOMMON 0 0 DATA 2 27 EN DATA @@ -271,13 +289,13 @@ MEV MB 19.5 47.1 20. 54.6 ENDDATA 29 -ENDSUBENT 38 -SUBENT M0539009 20010504 20010711 20050926 0000 +ENDSUBENT 43 +SUBENT M0539009 20110512 20111003 20110921 M059 BIB 2 4 -REACTION (73-TA-181(G,X)0-NN-1,UNW,INT,,BRS,EXP) - THE SUM OF THE (G,N), (G,NP), AND (G,2N) REACTION - CROSS SECTIONS. -ERR-ANALYS NO INFORMATION. +REACTION (73-TA-181(G,X)0-NN-1,UNW,INT,,BRS) + The sum of the (g,n), (g,np), and (g,2n) reaction + cross sections. +ERR-ANALYS No information. ENDBIB 4 NOCOMMON 0 0 DATA 3 1 @@ -286,10 +304,10 @@ MEV MEV MB*MEV 8. 20. 2300. ENDDATA 3 ENDSUBENT 12 -SUBENT M0539010 20010504 20010711 20050926 0000 +SUBENT M0539010 20110512 20111003 20110921 M059 BIB 2 2 -REACTION (73-TA-181(G,2N)73-TA-179,,INT,,BRS,EXP) -ERR-ANALYS NO INFORMATION. +REACTION (73-TA-181(G,2N)73-TA-179,,INT,,BRS) +ERR-ANALYS No information. ENDBIB 2 NOCOMMON 0 0 DATA 3 1 @@ -298,12 +316,12 @@ MEV MEV MB*MEV 14. 20. 1100. ENDDATA 3 ENDSUBENT 10 -SUBENT M0539011 20010504 20010711 20050926 0000 +SUBENT M0539011 20110512 20111003 20110921 M059 BIB 2 4 -REACTION (83-BI-209(G,X)0-NN-1,UNW,INT,,BRS,EXP) - THE SUM OF THE (G,N), (G,NP), AND (G,2N) REACTION - CROSS SECTIONS. -ERR-ANALYS NO INFORMATION. +REACTION (83-BI-209(G,X)0-NN-1,UNW,INT,,BRS) + The sum of the (g,n), (g,np), and (g,2n) reaction + cross sections. +ERR-ANALYS No information. ENDBIB 4 NOCOMMON 0 0 DATA 3 1 diff --git a/exforall/M06/M0619.x4 b/exforall/M06/M0619.x4 index 0b150211f..6e753b1b3 100644 --- a/exforall/M06/M0619.x4 +++ b/exforall/M06/M0619.x4 @@ -1,166 +1,170 @@ -ENTRY M0619 20010322 20010711 20050926 0000 -SUBENT M0619001 20010322 20010711 20050926 0000 -BIB 13 19 -TITLE INTEGRAL CROSS SECTIONS OF THE PHOTONUCLEAR REACTIONS - IN THE REGION OF GIANT DIPOLE RESONANCE. -AUTHOR (A.G.BELOV,YU.P.GANGRSKY,K.K.GUDIMA,P.ZUZAAN) +ENTRY M0619 20110531 20111003 20110921 M059 +SUBENT M0619001 20110531 20111003 20110921 M059 +BIB 13 23 +TITLE Integral cross sections of the photonuclear reactions + in the region of giant dipole resonance. +AUTHOR (A.G.Belov,Yu.P.Gangrsky,K.K.Gudima,P.Zuzaan) REFERENCE (J,AE,88,391,2000) + (J,AE/T,88,408,2000) + English translation of AE,88,391,2000. INSTITUTE (4ZZZDUB) FACILITY (MICRT,4ZZZDUB) INC-SOURCE (BRST) METHOD (ACTIV) DETECTOR (GELI) 60 SM*3. -ANALYSIS (AREA) CODE ACTIV USED. -ERR-ANALYS (DATA-ERR) MEAN-WEIGHTED ERRORS OF ABOUT 10 PERCENT: - STATISTICAL ERRORS, ELECTRON BEAM INTENSITY, G-LINE - SQUARE AFTER THE BACKGROUND SUBTRACTION, ETC. -COMMENT INTEGRATED PHOTONUCLEAR REACTION CROSS SWECTIONS WERE - MEASURED USING BREMSSTRAHLUNG FOR THE 12 TARGET - NUCLEI. -STATUS (TABLE) DATA FROM THE TABLE 3 WERE COMPILED AT THE - RUSSIA MSU INP CDFE BY V.VARLAMOV. +ANALYSIS (AREA) Code ACTIV used. +ERR-ANALYS (DATA-ERR) Mean-weighted errors of about 10 percent: + statistical errors, electron beam intensity, g-line + square after the background subtraction, etc. +COMMENT Integrated photonuclear reaction cross sections were + measured using bremsstrahlung for the 12 target + nuclei. +STATUS (TABLE) Data from the Table 3 were compiled at the + RUSSIA MSU INP CDFE by V.Varlamov. HISTORY (20010321C) -ENDBIB 19 -NOCOMMON -ENDSUBENT 22 -SUBENT M0619002 20010322 20010711 20050926 0000 + (20110531A) Corrected by V.Varlamov: REFERENCE, BRS + -> BRA, lowercase. +ENDBIB 23 +NOCOMMON 0 0 +ENDSUBENT 26 +SUBENT M0619002 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (21-SC-45(G,N)21-SC-44,,INT,,BRS,EXP) -SAMPLE METALL TARGET (100 %), 80 G THICKNESS. +REACTION (21-SC-45(G,N)21-SC-44,,INT,,BRA) +SAMPLE Metal target (100 %), 80 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV 25. 340. 30. ENDDATA 3 ENDSUBENT 10 -SUBENT M0619003 20010322 20010711 20050926 0000 +SUBENT M0619003 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (27-CO-59(G,N)27-CO-58,,INT,,BRS,EXP) -SAMPLE METALL TARGET (100 %), 115 G THICKNESS. +REACTION (27-CO-59(G,N)27-CO-58,,INT,,BRA) +SAMPLE Metal target (100 %), 115 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV 25. 405. 40. ENDDATA 3 ENDSUBENT 10 -SUBENT M0619004 20010322 20010711 20050926 0000 +SUBENT M0619004 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (29-CU-63(G,N)29-CU-62,,INT,,BRS,EXP) -SAMPLE METALL TARGET (69.1 %), 140 G THICKNESS. +REACTION (29-CU-63(G,N)29-CU-62,,INT,,BRA) +SAMPLE Metal target (69.1 %), 140 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV 25. 510. 40. ENDDATA 3 ENDSUBENT 10 -SUBENT M0619005 20010322 20010711 20050926 0000 +SUBENT M0619005 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (39-Y-89(G,N)39-Y-88,,INT,,BRS,EXP) -SAMPLE Y(N0-3)-3 TARGET (100 %), 35 G THICKNESS. +REACTION (39-Y-89(G,N)39-Y-88,,INT,,BRA) +SAMPLE Y(N0-3)-3 target (100 %), 35 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV 25. 530. 50. ENDDATA 3 ENDSUBENT 10 -SUBENT M0619006 20010322 20010711 20050926 0000 +SUBENT M0619006 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (40-ZR-90(G,N)40-ZR-89,,INT,,BRS,EXP) -SAMPLE METALL TARGET (51.5 %), 120 G THICKNESS. +REACTION (40-ZR-90(G,N)40-ZR-89,,INT,,BRA) +SAMPLE Metal target (51.5 %), 120 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV 25. 520. 50. ENDDATA 3 ENDSUBENT 10 -SUBENT M0619007 20010322 20010711 20050926 0000 +SUBENT M0619007 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (46-PD-110(G,N)46-PD-109,,INT,,BRS,EXP) -SAMPLE METALL TARGET (13.5 %), 105 G THICKNESS. +REACTION (46-PD-110(G,N)46-PD-109,,INT,,BRA) +SAMPLE Metal target (13.5 %), 105 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV 25. 1100. 100. ENDDATA 3 ENDSUBENT 10 -SUBENT M0619008 20010322 20010711 20050926 0000 +SUBENT M0619008 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (55-CS-133(G,N)55-CS-132,,INT,,BRS,EXP) -SAMPLE CSCL TARGET (100 %), 90 G THICKNESS. +REACTION (55-CS-133(G,N)55-CS-132,,INT,,BRA) +SAMPLE CSCL target (100 %), 90 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV 25. 1450. 100. ENDDATA 3 ENDSUBENT 10 -SUBENT M0619009 20010322 20010711 20050926 0000 +SUBENT M0619009 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (56-BA-132(G,N)56-BA-131,,INT,,BRS,EXP) -SAMPLE BA(NO-3)-2 TARGET (67 %), 55 G THICKNESS. +REACTION (56-BA-132(G,N)56-BA-131,,INT,,BRA) +SAMPLE BA(NO-3)-2 target (67 %), 55 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV 25. 1550. 120. ENDDATA 3 ENDSUBENT 10 -SUBENT M0619010 20010322 20010711 20050926 0000 +SUBENT M0619010 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (58-CE-140(G,N)58-CE-139,,INT,,BRS,EXP) -SAMPLE CE-2,O-3 TARGET (88.5 %), 110 G THICKNESS. +REACTION (58-CE-140(G,N)58-CE-139,,INT,,BRA) +SAMPLE CE-2,O-3 target (88.5 %), 110 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV 25. 1900. 150. ENDDATA 3 ENDSUBENT 10 -SUBENT M0619011 20010322 20010711 20050926 0000 +SUBENT M0619011 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (60-ND-148(G,N)60-ND-147,,INT,,BRS,EXP) -SAMPLE ND-2,O-3 TARGET (93 %), 70 G THICKNESS. +REACTION (60-ND-148(G,N)60-ND-147,,INT,,BRA) +SAMPLE ND-2,O-3 target (93 %), 70 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV 25. 1980. 200. ENDDATA 3 ENDSUBENT 10 -SUBENT M0619012 20010322 20010711 20050926 0000 +SUBENT M0619012 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (79-AU-197(G,N)79-AU-196,,INT,,BRS,EXP) -SAMPLE METALL TARGET (100 %), 65 G THICKNESS. +REACTION (79-AU-197(G,N)79-AU-196,,INT,,BRA) +SAMPLE Metal target (100 %), 65 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV 25. 2350. 200. ENDDATA 3 ENDSUBENT 10 -SUBENT M0619013 20010322 20010711 20050926 0000 +SUBENT M0619013 20110531 20111003 20110921 M059 BIB 2 2 -REACTION (82-PB-204(G,N)82-PB-203,,INT,,BRS,EXP) -SAMPLE METALL TARGET (87 %), 60 G THICKNESS. +REACTION (82-PB-204(G,N)82-PB-203,,INT,,BRA) +SAMPLE Metal target (87 %), 60 g thickness. ENDBIB 2 -NOCOMMON +NOCOMMON 0 0 DATA 3 1 EN-MAX DATA DATA-ERR MEV MB*MEV MB*MEV diff --git a/exforall/M07/M0749.x4 b/exforall/M07/M0749.x4 index ced21340b..3b3ec98de 100644 --- a/exforall/M07/M0749.x4 +++ b/exforall/M07/M0749.x4 @@ -1,27 +1,30 @@ -ENTRY M0749 20080807 20081028 20081023 M046 -SUBENT M0749001 20080807 20081028 20081023 M046 -BIB 13 17 -TITLE Isomeric yield ratios for the reaction - 89Y(g,2n)87mgY. -AUTHOR (S.R.PALVANOV,O.RAZHABOV) -REFERENCE (J,AE,84,(3),278,1998) -INSTITUTE (4UZ UZ) National University of Uzbekistan Researh +ENTRY M0749 20110606 20111003 20110921 M059 +SUBENT M0749001 20110606 20111003 20110921 M059 +BIB 13 20 +TITLE Isomeric yield ratios for the reactions + 89Y(g,2n)87Y-mg. +AUTHOR (S.R.Palvanov,O.Razhabov) +REFERENCE (J,AE,84,278,1998) + (J,AE/T,84,222,1998) + English translation of AE,84,278,1998. +INSTITUTE (4UZ UZ) National University of Uzbekistan Research Institute of Applied Physics. -FACILITY (BETAT,4UZ UZ) The SB-50 betatron of National - University of Uzbekistan RIAP. +FACILITY (BETAT,4UZ UZ) The SB-50 betatron of National + University of Uzbekistan RIAP. INC-SOURCE (BRST) SAMPLE Y2O3 with weight ~ 2 - 3 g. -DETECTOR (SOLST) Simiconductor detector DGDK-63V. +DETECTOR (SOLST) Semiconductor detector DGDK-63V. METHOD (ACTIV) Induced gamma-activity measured. ANALYSIS (AREA) ERR-ANALYS (ERR-S) Statistical errors. -STATUS (CURVE) Data from the Figure have been compiled at +STATUS (CURVE) Data from the figure have been compiled at the Russia MSU SINP CDFE by V.Varlamov. HISTORY (20080806C) -ENDBIB 17 + (20110606A) Corrected by V.Varlamov: REFERENCE. +ENDBIB 20 NOCOMMON 0 0 -ENDSUBENT 20 -SUBENT M0749002 20080807 20081028 20081023 M046 +ENDSUBENT 23 +SUBENT M0749002 20110606 20111003 20110921 M059 BIB 2 3 REACTION (39-Y-89(G,2N)39-Y-87-M/G,,SIG/RAT,,BRA) DECAY-DATA (39-Y-87-M,13.0HR,DG,381.0) diff --git a/exforall/M08/M0803.x4 b/exforall/M08/M0803.x4 new file mode 100644 index 000000000..75f16c90e --- /dev/null +++ b/exforall/M08/M0803.x4 @@ -0,0 +1,63 @@ +ENTRY M0803 20110607 20111003 20110921 M059 +SUBENT M0803001 20110607 20111003 20110921 M059 +BIB 14 20 +TITLE Photodisintegration of Sn isotopes. +AUTHOR (B.S.Ishkhanov,S.Yu.Troshchiev,V.A.Tchetvertkova) +REFERENCE (J,IZV,75,594,2011) + (J,BAS,75,558,2011) + English translation of IZV,75,594,2011. +INSTITUTE (4RUSMOS) +FACILITY (MICRT,4RUSMOS) 70 MeV racetrack microtron RTM-70, + Skobeltsyn Institute of Nuclear Physics, Lomonosov + Moscow State University. +REL-REF (I,M0738001,A.N.ERMAKOV+,J,YF,71,419,2008) + General description of facility and detector. +INC-SOURCE (BRST) +SAMPLE Natural Sn sample. +METHOD (ACTIV) Induced beta-delayed g-activity measured. +DETECTOR (HPGE) +ANALYSIS (AREA) Gamma-quanta energy spectrum lines data. +ERR-ANALYS (DATA-ERR) Root-mean-square errors. +STATUS (TABLE,APRVD) Data from Table 2, by S.Yu.Troshchiev. +HISTORY (20110607C) Data from the Table 2 were compiled at + the Russia MSU SINP CDFE by V.Varlamov. +ENDBIB 20 +COMMON 1 3 +EN-MAX +MEV + 19.5 +ENDCOMMON 3 +ENDSUBENT 27 +SUBENT M0803002 20110607 20111003 20110921 M059 +BIB 3 16 +REACTION (50-SN-0(G,X)ELEM/MASS,,SIG,,BRA/REL) +DECAY-DATA (49-IN-111,2.8047D) + (49-IN-115-M,4.486HR) + (49-IN-116-M,54.29MIN) + (50-SN-111,35.3MIN) + (50-SN-113,115.09D) + (50-SN-117-M,13.6D) + (50-SN-123-M,40.06MIN) +COMMENT Authors nominate correspondingly the following + reactions: (50-SN-112(G,P)49-IN-111) + (50-SN-116(G,P)49-IN-115-M) + (50-SN-117(G,P)49-IN-116-M) + (50-SN-112(G,N)50-SN-111) + (50-SN-114(G,N)50-SN-113) + (50-SN-118(G,N)50-SN-117-M) + (50-SN-124(G,N)50-SN-123-M) +ENDBIB 16 +NOCOMMON 0 0 +DATA 5 7 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM ARB-UNITS ARB-UNITS + 49. 111. .0017 .0005 + 49. 115. 1. .00433 .00026 + 49. 116. 1. .000958 .000057 + 50. 111. 1. .09 + 50. 113. 1.534 .245 + 50. 117. 1. .102 .007 + 50. 123. 1. 1.89 .21 +ENDDATA 9 +ENDSUBENT 30 +ENDENTRY 2 diff --git a/exforall/M08/M0804.x4 b/exforall/M08/M0804.x4 index 7c3adf45f..c1a41f626 100644 --- a/exforall/M08/M0804.x4 +++ b/exforall/M08/M0804.x4 @@ -1,6 +1,6 @@ -ENTRY M0804 20110224 20110518 20110427 M057 -SUBENT M0804001 20110224 20110518 20110427 M057 -BIB 14 28 +ENTRY M0804 20110504 20111003 20110921 M059 +SUBENT M0804001 20110504 20111003 20110921 M059 +BIB 14 29 TITLE New experimental method for investigation of the nucleon polarizabilities. AUTHOR (O.Yevetska,S.Watzlawik,J.Ahrens,G.D.Alkhazov, @@ -21,7 +21,7 @@ SAMPLE Hydrogen gas of high purity (99.9999 %) at a pressure DETECTOR (IOCH,NAICR) High pressure ionization chambers and NaI(Tl) photon spectrometer. METHOD (EXTB,SITA,COINC) -PART-DET (P) +PART-DET (G,P) ERR-ANALYS (ERR-S) Statistical errors. COMMENT The whole experimental setup for investigation of nucleon polarizabilities was tested by measurements @@ -29,13 +29,14 @@ COMMENT The whole experimental setup for investigation of STATUS (CURVE) Data from Fig. 12 were compiled at the Russia MSU SINP CDFE by V.Varlamov. HISTORY (20110224C) -ENDBIB 28 + (20110504A) Corrected by V.Varlamov: PART-DET. +ENDBIB 29 COMMON 1 3 ANG ADEG 130. ENDCOMMON 3 -ENDSUBENT 35 +ENDSUBENT 36 SUBENT M0804002 20110224 20110518 20110427 M057 BIB 1 1 REACTION (1-H-1(G,EL)1-H-1,,DA) diff --git a/exforall/M08/M0807.x4 b/exforall/M08/M0807.x4 new file mode 100644 index 000000000..7c127a68b --- /dev/null +++ b/exforall/M08/M0807.x4 @@ -0,0 +1,67 @@ +ENTRY M0807 20110607 20111003 20110921 M059 +SUBENT M0807001 20110607 20111003 20110921 M059 +BIB 14 22 +TITLE Yields of photonuclear reactions on Hg isotopes under + a bremsstrahlung beam with a maximum energy of 29.1 + MeV. +AUTHOR (B.S.Ishkhanov,S.Yu.Troshchiev) +REFERENCE (J,IZV,75,603,2011) + (J,BAS,75,566,2011) + English translation of IZV,75,603,2011. +INSTITUTE (4RUSMOS) +FACILITY (MICRT,4RUSMOS) 70 MeV racetrack microtron RTM-70, + Skobeltsyn Institute of Nuclear Physics, Lomonosov + Moscow State University. +REL-REF (I,M0738001,A.N.ERMAKOV+,J,YF,71,419,2008) + General description of facility and detector. +INC-SOURCE (BRST) +SAMPLE Natural Hg sample. +METHOD (ACTIV) Induced beta-delayed g-activity measured. +DETECTOR (HPGE) +ANALYSIS (AREA) Gamma-quanta energy spectrum lines data. +ERR-ANALYS (DATA-ERR) Root-mean-square errors. +STATUS (TABLE,APRVD) By S.Yu.Troshchiev. +HISTORY (20110607C) Data from the table were compiled at the + Russia MSU SINP CDFE by V.Varlamov. +ENDBIB 22 +COMMON 1 3 +EN-MAX +MEV + 29.1 +ENDCOMMON 3 +ENDSUBENT 29 +SUBENT M0807002 20110607 20111003 20110921 M059 +BIB 2 14 +REACTION ((80-HG-198(G,X)ELEM/MASS,,SIG,,BRA)/ + (80-HG-196(G,N)80-HG-195,,SIG,,BRA)) +COMMENT Authors nominate correspondingly the following + reactions: (80-HG-198(G,NP)79-AU-196) + (80-HG-199(G,P)79-AU-198) + (90-HG-200(G,P)79-AU-199) + (90-HG-201(G,P)79-AU-200) + (90-HG-202(G,P)79-AU-201) + (90-HG-196(G,N)90-HG-195) + (90-HG-196(G,N)90-HG-195-M) + (90-HG-198(G,N)90-HG-197) + (90-HG-198(G,N)90-HG-197-M) + (90-HG-200(G,N)90-HG-199-M) + (90-HG-204(G,N)90-HG-203) +ENDBIB 14 +NOCOMMON 0 0 +DATA 5 11 +ELEMENT MASS ISOMER DATA DATA-ERR +NO-DIM NO-DIM NO-DIM ARB-UNITS ARB-UNITS + 79. 196. .00006 .00002 + 79. 198. .0027 .0005 + 79. 199. .0028 .0006 + 79. 200. .0024 .0005 + 79. 201. .0014 .0007 + 80. 195. .88 .2 + 80. 195. 1. .12 .03 + 80. 197. 1.27 .29 + 80. 197. 1. .15 .03 + 80. 199. 1. .085 .017 + 80. 203. 1.16 .23 +ENDDATA 13 +ENDSUBENT 32 +ENDENTRY 2 diff --git a/exforall/M08/M0814.x4 b/exforall/M08/M0814.x4 new file mode 100644 index 000000000..8cd8cac93 --- /dev/null +++ b/exforall/M08/M0814.x4 @@ -0,0 +1,122 @@ +ENTRY M0814 20110609 20111003 20110921 M059 +SUBENT M0814001 20110609 20111003 20110921 M059 +BIB 11 16 +TITLE Photoneutron cross sections of 90Zr and 91Zr. +AUTHOR (G.P.Antropov,I.E.Mitrofanov,A.I.Prokof'ev, + B.S.Russkikh) +INSTITUTE (4RUSFTI) +REFERENCE (J,IZV,33,700,1969) + (J,BAS,33,645,1970) English translation of IZV,33,700 +INC-SOURCE (BRST) +FACILITY (BETAT,4RUSFTI) 30 MeV betatron. +SAMPLE Zirconium oxide targets, 100 g, 90Zr (96/6 %), 91Zr + (63,6 %). +METHOD (EXTB,SITA) The reaction yield curve measurement. +DETECTOR (BF3) +ANALYSIS (UNFLD,PLA) The Penfold-Leiss method for cross + section unfolding from the yield curve. +HISTORY (20110609C) Data were compiled at the MSU SINP CDFE + by V.Varlamov. +ENDBIB 16 +NOCOMMON 0 0 +ENDSUBENT 19 +SUBENT M0814002 20110609 20111003 20110921 M059 +BIB 3 6 +REACTION ((40-ZR-90(G,N)40-ZR-89,,SIG,,BRS)+ + (40-ZR-90(G,N+P)39-Y-88,,SIG,,BRS)) + Threshold of reaction (g,np) is equal to 19.8 MeV, + that of reaction (g,2n) - to 21.3 MeV. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +STATUS (CURVE) Data from the Fig 1a. +ENDBIB 6 +NOCOMMON 0 0 +DATA 3 21 +EN DATA DATA-ERR +MEV MB MB + 12.0 5.4 2.2 + 12.5 16.2 2.27 + 13. 22.93 2.43 + 13.5 39.73 4.05 + 14. 55.14 4.21 + 14.5 83.53 6.49 + 15. 110.27 9. + 15.5 157.57 9.73 + 16. 221.12 8.43 + 16.5 252.97 9. + 17. 197.84 12.16 + 17.5 225.13 14.27 + 18. 212.94 16.22 + 18.5 155.68 15.4 + 19. 118.95 15.65 + 19.5 93.24 15.4 + 20. 63.24 15.4 + 20.5 25.14 14.6 + 21. 32.43 17.84 + 21.5 32.43 17.84 + 22. -18.65 20.27 +ENDDATA 23 +ENDSUBENT 34 +SUBENT M0814003 20110609 20111003 20110921 M059 +BIB 3 6 +REACTION (40-ZR-91(G,X)0-NN-1,,SIG,,BRS) + The sum (g,n) + (g,np) + 2(g,2n) reactions. + Threshold of reaction (g,np) is equal to 15.6 MeV, + that of reaction (g,2n) - to 19.6 MeV. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +STATUS (CURVE) Data from the Fig 1b. +ENDBIB 6 +NOCOMMON 0 0 +DATA 3 20 +EN DATA DATA-ERR +MEV MB MB + 12.0 3.82 2.29 + 12.5 8.4 4.48 + 13. 15.29 5. + 13.5 26.76 5.35 + 14. 43.24 5.31 + 14.5 88.73 6.89 + 15. 146.82 8.41 + 15.5 222.57 7.13 + 16. 267.65 9.18 + 16.5 207. 9. + 17. 146. 11.76 + 17.5 176.66 12.27 + 18. 206.47 13.76 + 18.5 168.24 14.53 + 19. 116.25 15.25 + 19.5 73.44 14.4 + 20. 30.62 14.53 + 20.5 13.8 13.7 + 21. 64.88 16. + 21.5 82.59 14.54 +ENDDATA 22 +ENDSUBENT 33 +SUBENT M0814004 20110609 20111003 20110921 M059 +BIB 3 4 +REACTION ((40-ZR-90(G,N)40-ZR-89,,INT,,BRA)+ + (40-ZR-90(G,N+P)39-Y-88,,INT,,BRA)) +ERR-ANALYS No information. +STATUS (TABLE) Data from the Table 1. +ENDBIB 4 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 22.5 1270. +ENDDATA 3 +ENDSUBENT 12 +SUBENT M0814005 20110609 20111003 20110921 M059 +BIB 3 4 +REACTION ((40-ZR-91(G,N)40-ZR-90,,INT,,BRA)+ + (40-ZR-91(G,N+P)39-Y-89,,INT,,BRA)) +ERR-ANALYS No information. +STATUS (TABLE) Data from the Table 1. +ENDBIB 4 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 22.5 1420. +ENDDATA 3 +ENDSUBENT 12 +ENDENTRY 5 diff --git a/exforall/M08/M0815.x4 b/exforall/M08/M0815.x4 new file mode 100644 index 000000000..e11dd2219 --- /dev/null +++ b/exforall/M08/M0815.x4 @@ -0,0 +1,148 @@ +ENTRY M0815 20110610 20111003 20110921 M059 +SUBENT M0815001 20110610 20111003 20110921 M059 +BIB 14 42 +TITLE Photoneutron reaction cross sections of 64,66,68Zn, + 70,72,74,76Ge, 76,78,80,82Se. +AUTHOR (A.M.Goryachev,G.N.Zalesny,B.A.Tulupov) +INSTITUTE (4RUSSGU) +REFERENCE (J,IZV,39,134,1975) + (J,BAS,39,116,1975) + English translation of IZV,39,134,1975 +FACILITY (BETAT,4RUSSGU) +INC-SOURCE (BRST) +SAMPLE Nucleus Enrichment,% Height, g Admixtures, % + 64Zn 90. 8.43 66Zn - 7.1 + 68Zn - 1.9 + 66Zn 90.4 12.06 64Zn - 5.2 + 68Zn - 2.0 + 68Zn 86.8 15.55 64Zn - 3.3 + 66Zn - 7.9 + 70Ge 86.5 10.79 72Ge - 5.0 + 74Ge - 5.7 + 72Ge 90.1 5.72 70Ge - 2.4 + 74Ge - 4.7 + 74Ge 91. 9.93 72Ge - 3.1 + 76Ge - 2.2 + 76Ge 76. 10. 78Ge - 9.8 + 72Ge - 6.7 + 76Se 78.6 4.9 78Se - 8.4 + 80Se - 8.8 + 78Se 87.8 15.5 77Se - 1.5 + 80Se - 8.2 + 80Se 95.7 12.03 78Se - 1.8 + 82Se - 1.4 + 82Se 76.7 6.95 78Se - 4.2 + 80Se - 17.4 +METHOD (EXTB,SITA) +DETECTOR (BF3) +ANALYSIS (UNFLD,PLA) +CORRECTION The correction for multipole neutron emission in the + (g,2n) process was applied using the statistical + theory. +ERR-ANALYS (DATA-ERR) Root-mean-squared uncertainties. +STATUS (CURVE) +HISTORY (20110610C) Data were compiled at the Russia MSU SINP + CDFE by V.Varlamov. +ENDBIB 42 +NOCOMMON 0 0 +ENDSUBENT 45 +SUBENT M0815002 20110610 20111003 20110921 M059 +BIB 2 3 +REACTION ((30-ZN-64(G,N)30-ZN-63,,SIG,,BRS)+ + (30-ZN-64(G,N+P)29-CU-62,,SIG,,BRS)) +STATUS (SPSDD,M0070002) +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 +SUBENT M0815003 20110610 20111003 20110921 M059 +BIB 2 3 +REACTION ((30-ZN-66(G,N)30-ZN-65,,SIG,,BRS)+ + (30-ZN-66(G,N+P)29-CU-64,,SIG,,BRS)) +STATUS (SPSDD,M0070003) +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 +SUBENT M0815004 20110610 20111003 20110921 M059 +BIB 2 3 +REACTION ((30-ZN-68(G,N)30-ZN-67,,SIG,,BRS)+ + (30-ZN-68(G,N+P)29-CU-66,,SIG,,BRS)) +STATUS (SPSDD,M0070005) +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 +SUBENT M0815005 20110610 20111003 20110921 M059 +BIB 2 3 +REACTION ((32-GE-70(G,N)32-GE-69,,SIG,,BRS)+ + (32-GE-70(G,N+P)31-GA-68,,SIG,,BRS)) +STATUS (SPSDD,M0070007) +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 +SUBENT M0815006 20110610 20111003 20110921 M059 +BIB 2 3 +REACTION ((32-GE-72(G,N)32-GE-71,,SIG,,BRS)+ + (32-GE-72(G,N+P)31-GA-70,,SIG,,BRS)) +STATUS (SPSDD,M0070008) +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 +SUBENT M0815007 20110610 20111003 20110921 M059 +BIB 2 3 +REACTION ((32-GE-74(G,N)32-GE-73,,SIG,,BRS)+ + (32-GE-74(G,N+P)31-GA-72,,SIG,,BRS)) +STATUS (SPSDD,M0070010) +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 +SUBENT M0815008 20110610 20111003 20110921 M059 +BIB 2 3 +REACTION ((32-GE-76(G,N)32-GE-75,,SIG,,BRS)+ + (32-GE-76(G,N+P)31-GA-74,,SIG,,BRS)) +STATUS (SPSDD,M0070011) +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 +SUBENT M0815009 20110610 20111003 20110921 M059 +BIB 2 3 +REACTION ((34-SE-76(G,N)34-SE-75,,SIG,,BRS)+ + (34-SE-76(G,N+P)33-AS-74,,SIG,,BRS)) +STATUS (SPSDD,M0070013) +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 +SUBENT M0815010 20110610 20111003 20110921 M059 +BIB 2 3 +REACTION ((34-SE-78(G,N)34-SE-77,,SIG,,BRS)+ + (34-SE-78(G,N+P)33-AS-76,,SIG,,BRS)) +STATUS (SPSDD,M0070015) +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 +SUBENT M0815011 20110610 20111003 20110921 M059 +BIB 2 3 +REACTION ((34-SE-80(G,N)34-SE-79,,SIG,,BRS)+ + (34-SE-80(G,N+P)33-AS-78,,SIG,,BRS)) +STATUS (SPSDD,M0070016) +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 +SUBENT M0815012 20110610 20111003 20110921 M059 +BIB 2 3 +REACTION ((34-SE-82(G,N)34-SE-81,,SIG,,BRS)+ + (34-SE-82(G,N+P)33-AS-80,,SIG,,BRS)) +STATUS (SPSDD,M0070017) +ENDBIB 3 +NOCOMMON 0 0 +NODATA 0 0 +ENDSUBENT 7 +ENDENTRY 12 diff --git a/exforall/M08/M0816.x4 b/exforall/M08/M0816.x4 new file mode 100644 index 000000000..eff5fa33a --- /dev/null +++ b/exforall/M08/M0816.x4 @@ -0,0 +1,840 @@ +ENTRY M0816 20110614 20111003 20110921 M059 +SUBENT M0816001 20110614 20111003 20110921 M059 +BIB 11 22 +TITLE Giant resonance in the energy region of transition + from spherical nuclei to deformed ones. +AUTHOR (O.V.Vasilyev,G.N.Zalesny,S.F.Semenko,V.A.Semenov) +INSTITUTE (4RUSSGU) +REFERENCE (J,YF,10,460,1969) + (J,SNP,10,263,1969) + English translation of YF,10,460,1969. +FACILITY (BETAT,4RUSSGU) Saratov State University betatron + with maximum energy 25 MeV. +SAMPLE Monoisotopic oxides (X-2,O-3): + Isotope Enrichment, % Height, g + 148Nd 89.4 4.31 + 150Nd 90.3 4.43 + 150Sm 89. 1.89 + 152Sm 96.9 1.56 + 154Sm 98.2 4.51 +INC-SOURCE (BRST) +DETECTOR (PROPC) 6 proportional counters. +METHOD (EXTB,SITA) +STATUS (CURVE,APRVD) Data from Fig. 2, by S.F.Semenko. +HISTORY (20110614C) Data were compiled at the Russia MSU SIMP + CDFE by V.Varlamov. +ENDBIB 22 +NOCOMMON 0 0 +ENDSUBENT 25 +SUBENT M0816002 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (60-ND-148(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 60 +EN DATA DATA-ERR +MEV MB MB + 7.5 36.59 7.68 + 7.75 51.22 7.5 + 8. 71.3 7.66 + 8.25 8.2 8.2 + 8.5 52.72 8.23 + 8.75 64.28 8.4 + 9. 84.98 8.3 + 9.25 84.92 7.68 + 9.5 107.93 7.87 + 9.75 100.6 8.23 + 10. 111.59 8.23 + 10.25 98.78 7.5 + 10.5 140.85 8. + 10.75 165.15 7.3 + 11. 191.16 7.4 + 11.25 192.15 8.4 + 11.5 184.76 8.8 + 11.75 195.84 8.27 + 12. 232.32 9.88 + 12.25 265.24 10. + 12.5 303.77 7.32 + 12.75 332.56 10.98 + 13. 356.7 11. + 13.25 389.49 13.17 + 13.5 454.54 + 13.75 516.37 + 14. 567. + 14.25 592.68 + 14.5 565.24 + 14.75 512.2 + 15. 471.66 + 15.25 480.4 + 15.5 513.7 + 15.75 545. + 16. 531. + 16.25 462.88 + 16.5 396.95 + 16.75 289. + 17. 215.85 + 17.25 190.24 + 17.5 146.34 + 17.75 161. + 18. 171.95 + 18.25 153.66 + 18.5 148.17 + 18.75 115.35 + 19. 60.59 + 19.25 75. + 19.5 100.6 + 19.75 133.02 + 20. 187.72 + 20.25 157.32 + 20.5 155.2 + 20.75 168.29 + 21.25 209.9 + 21.5 204.88 + 21.75 186.59 + 22. 186.4 + 22.25 184.76 + 22.5 204.88 +ENDDATA 62 +ENDSUBENT 72 +SUBENT M0816003 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (60-ND-148(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0816002) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 62 +EN DATA DATA-ERR +MEV MB MB + 7.5 36.59 7.68 + 7.75 51.22 7.5 + 8. 71.3 7.66 + 8.25 8.2 8.2 + 8.5 52.72 8.23 + 8.75 64.28 8.4 + 9. 84.98 8.3 + 9.25 84.92 7.68 + 9.5 107.93 7.87 + 9.75 100.6 8.23 + 10. 111.59 8.23 + 10.25 98.78 7.5 + 10.5 140.85 8. + 10.75 165.15 7.3 + 11. 191.16 7.4 + 11.25 192.15 8.4 + 11.5 184.76 8.8 + 11.75 195.84 8.27 + 12. 232.32 9.88 + 12.25 265.24 10. + 12.5 303.77 7.32 + 12.75 332.56 10.98 + 13. 356.7 11. + 13.25 389.49 13.17 + 13.5 440.85 14.63 + 13.75 439. 15.18 + 14. 422.56 12.8 + 14.25 393.18 12.8 + 14.5 343.9 14.38 + 14.75 294.51 14.5 + 15. 264.4 14.6 + 15.25 256. 14.4 + 15.5 268.9 13.9 + 15.75 276.48 13.72 + 16. 272.56 12.8 + 16.25 234.15 10. + 16.5 181. 14.4 + 16.75 146.34 12.8 + 17. 109.76 12.8 + 17.25 93.37 12.18 + 17.5 82.4 10.9 + 17.75 84.15 11.45 + 18. 88.68 11. + 18.25 80.2 11.7 + 18.5 74.71 10.9 + 18.75 59.12 12.8 + 19. 32.93 13.2 + 19.25 40. 13.65 + 19.5 53.05 12.55 + 19.75 69.51 13.28 + 20. 96.07 14. + 20.25 78.73 12.8 + 20.5 81.29 11.89 + 20.75 86. 13.17 + 21. 84.15 13.2 + 21.25 107.93 11.52 + 21.5 106. 10.98 + 21.75 97.39 12.18 + 22. 96. 12.9 + 22.25 95.12 12.44 + 22.5 106.1 12.62 + 22.75 120.73 12.07 +ENDDATA 64 +ENDSUBENT 76 +SUBENT M0816004 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (60-ND-150(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 60 +EN DATA DATA-ERR +MEV MB MB + 8. 64.22 6.6 + 8.25 91.52 7.34 + 8.5 102.75 8. + 8.75 87.1 7.5 + 9. 91.74 8.26 + 9.25 97.25 5.9 + 9.5 111.93 7.4 + 9.75 131.93 7.37 + 10. 139.19 7.35 + 10.25 155.67 7.16 + 10.5 168.8 7.7 + 10.75 190.83 7.6 + 11. 214.5 7.41 + 11.25 222.39 6.6 + 11.5 231.19 6.8 + 11.75 234.61 8.88 + 12. 231.19 7.4 + 12.25 234.86 7.71 + 12.5 249.54 9.9 + 12.75 289.1 10.75 + 13. 339.45 + 13.25 390.83 + 13.5 436.7 + 13.75 460.62 + 14. 500. + 14.25 528.44 + 14.5 552.48 + 14.75 528.44 + 15. 563.3 + 15.25 459.63 + 15.5 506.42 + 15.75 612.84 + 16. 568.8 + 16.25 489.91 + 16.5 389.21 + 16.75 271.56 + 17. 177.9 + 17.25 161.98 + 17.5 146.8 + 17.75 144.55 + 18. 181.61 + 18.25 212.8 + 18.5 207.56 + 18.75 216.51 + 19. 207. + 19.25 135.78 + 19.5 88.95 + 19.75 32.59 + 20. 28.51 + 20.25 82.28 + 20.5 101. + 20.75 165.14 + 21. 141.28 + 21.25 77.83 + 21.5 51.38 + 21.75 33. + 22. 18.35 + 22.25 33. + 22.5 71.53 + 22.75 183.5 +ENDDATA 62 +ENDSUBENT 72 +SUBENT M0816005 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (60-ND-150(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0816004) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 60 +EN DATA DATA-ERR +MEV MB MB + 8. 64.22 6.6 + 8.25 91.52 7.34 + 8.5 102.75 8. + 8.75 87.1 7.5 + 9. 91.74 8.26 + 9.25 97.25 5.9 + 9.5 111.93 7.4 + 9.75 131.93 7.37 + 10. 139.19 7.35 + 10.25 155.67 7.16 + 10.5 168.8 7.7 + 10.75 190.83 7.6 + 11. 214.5 7.41 + 11.25 222.39 6.6 + 11.5 231.19 6.8 + 11.75 234.61 8.88 + 12. 231.19 7.4 + 12.25 234.86 7.71 + 12.5 249.54 9.9 + 12.75 289.1 10.75 + 13. 332.11 9.25 + 13.25 337.61 11.74 + 13.5 334.64 10.64 + 13.75 311.93 12.12 + 14. 308.26 12.2 + 14.25 307.63 12.11 + 14.5 304.6 11.6 + 14.75 291.74 12.22 + 15. 258.72 12. + 15.25 236.7 12.8 + 15.5 258.72 11. + 15.75 308. 12.9 + 16. 282.83 12.84 + 16.25 245.87 11.93 + 16.5 194.5 11.49 + 16.75 137.14 11.11 + 17. 88.08 10.83 + 17.25 82.64 9.19 + 17.5 77.06 10.28 + 17.75 77.83 12.5 + 18. 93.58 11.49 + 18.25 109.43 9.21 + 18.5 110. 9.98 + 18.75 111.93 10.72 + 19. 106.13 11. + 19.25 69.72 11. + 19.5 31.12 11. + 19.75 19.27 11.74 + 20. 16.51 11.11 + 20.25 44.81 9.72 + 20.5 55.05 11.2 + 20.75 84.4 11.3 + 21. 73.4 12.11 + 21.25 42.24 11.5 + 21.5 28.88 12.22 + 21.75 22. 10. + 22. 13.76 8. + 22.25 18.3 10. + 22.5 33.03 12.2 + 22.75 93.58 10.64 +ENDDATA 62 +ENDSUBENT 74 +SUBENT M0816006 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (62-SM-150(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 60 +EN DATA DATA-ERR +MEV MB MB + 8. 19.59 5.71 + 8.25 39.72 5.63 + 8.5 63.77 5.74 + 8.75 83.83 4.85 + 9. 86.05 5.7 + 9.25 86. 4.85 + 9.5 110.06 5.2 + 9.75 119.15 5.3 + 10. 134.6 5.52 + 10.25 134.73 5.74 + 10.5 142.63 6.62 + 10.75 169.37 6.6 + 11. 196.6 7.28 + 11.25 168.58 6.71 + 11.5 269.2 8.38 + 11.75 267. 8.8 + 12. 256. 8.16 + 12.25 260.37 8.83 + 12.5 247.13 8.8 + 12.75 277.67 9.71 + 13. 304.5 9.93 + 13.25 331. 11. + 13.5 333.33 11.92 + 13.75 321.8 11.9 + 14. 333.41 12.8 + 14.25 327.18 13.24 + 14.5 359.66 13.2 + 14.75 348.63 13.37 + 15. 333.19 + 15.25 364.08 + 15.5 350.88 + 15.75 410.55 + 16. 474.4 + 16.25 412.75 + 16.5 375.11 + 16.75 278.02 + 17. 163.28 + 17.25 148. + 17.5 117.2 + 17.75 145.28 + 18. 158.65 + 18.25 143.42 + 18.5 147.1 + 18.75 40.16 + 19. 37.86 + 19.25 46.38 + 19.5 12.89 + 19.75 48.54 + 20. 13.24 + 20.25 44.13 + 20.5 80.23 + 20.75 57. + 21. 66.2 + 21.25 90.57 + 21.5 39.72 + 21.75 54. + 22. 68. + 22.25 39. + 22.5 39.1 + 22.75 28.95 +ENDDATA 62 +ENDSUBENT 72 +SUBENT M0816007 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (62-SM-150(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0816006) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 60 +EN DATA DATA-ERR +MEV MB MB + 8. 19.59 5.71 + 8.25 39.72 5.63 + 8.5 63.77 5.74 + 8.75 83.83 4.85 + 9. 86.05 5.7 + 9.25 86. 4.85 + 9.5 110.06 5.2 + 9.75 119.15 5.3 + 10. 134.6 5.52 + 10.25 134.73 5.74 + 10.5 142.63 6.62 + 10.75 169.37 6.6 + 11. 196.6 7.28 + 11.25 168.58 6.71 + 11.5 269.2 8.38 + 11.75 267. 8.8 + 12. 256. 8.16 + 12.25 260.37 8.83 + 12.5 247.13 8.8 + 12.75 277.67 9.71 + 13. 304.5 9.93 + 13.25 331. 11. + 13.5 333.33 11.92 + 13.75 321.8 11.9 + 14. 333.41 12.8 + 14.25 327.18 13.24 + 14.5 359.66 13.2 + 14.75 348.63 13.37 + 15. 292.41 13.3 + 15.25 278. 10.81 + 15.5 249.34 11.47 + 15.75 260.37 11. + 16. 280.23 11.25 + 16.25 236.23 11.1 + 16.5 205.47 11.92 + 16.75 149.29 13.24 + 17. 88.26 11.7 + 17.25 77.23 11.72 + 17.5 61.47 11.92 + 17.75 75. 12.93 + 18. 80.23 14.12 + 18.25 71.32 13.37 + 18.5 72.86 13.68 + 18.75 17.83 14.56 + 19. 18.1 13.46 + 19.25 22.07 8.38 + 19.5 4.41 13.24 + 19.75 24.49 12.8 + 20. 4.45 14.56 + 20.25 17.65 15.45 + 20.5 37.42 13.46 + 20.75 26.48 14.56 + 21. 35.3 15. + 21.25 44.13 13.9 + 21.5 27.18 15.2 + 21.75 26.88 15.1 + 22. 35.3 15.45 + 22.25 19.6 14.12 + 22.5 22.07 13.37 + 22.75 13.24 10.37 +ENDDATA 62 +ENDSUBENT 74 +SUBENT M0816008 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (62-SM-152(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 57 +EN DATA DATA-ERR +MEV MB MB + 8.5 76.2 5.78 + 8.75 118.15 5.15 + 9. 134.26 5.55 + 9.25 162.04 6. + 9.5 171.3 6.2 + 9.75 185.37 5.2 + 10. 261.57 6.1 + 10.25 222.22 5.55 + 10.5 308.61 6.3 + 10.75 342.6 5.6 + 11. 366. 7. + 11.25 421.3 7. + 11.5 442.55 8.3 + 11.75 506.94 9. + 12. 509.26 10.65 + 12.25 446.76 9.26 + 12.5 360.97 12.5 + 12.75 284.31 14.81 + 13. 247.36 14.81 + 13.25 256.71 15.74 + 13.5 317.13 18.98 + 13.75 337.96 20.83 + 14. 348.38 21.3 + 14.25 402.78 21.76 + 14.5 439.54 21.3 + 14.75 496.16 21.53 + 15. 567.13 + 15.25 578.7 + 15.5 540.56 + 15.75 539.9 + 16. 518.52 + 16.25 460.6 + 16.5 456. + 16.75 370.37 + 17. 303.24 + 17.25 284.72 + 17.5 201.53 + 17.75 215.1 + 18. 175.79 + 18.25 136.57 + 18.5 152.78 + 18.75 115.74 + 19. 76.39 + 19.25 32.41 + 19.5 62.5 + 19.75 63.56 + 20. 46.3 + 20.25 50.93 + 20.5 25.46 + 20.75 143.52 + 21. 217.59 + 21.25 222.22 + 21.5 240.74 + 21.75 220.23 + 22. 213.24 + 22.25 190.46 + 22.5 157.14 +ENDDATA 59 +ENDSUBENT 69 +SUBENT M0816009 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (62-SM-152(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0816008) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 57 +EN DATA DATA-ERR +MEV MB MB + 8.5 76.2 5.78 + 8.75 118.15 5.15 + 9. 134.26 5.55 + 9.25 162.04 6. + 9.5 171.3 6.2 + 9.75 185.37 5.2 + 10. 261.57 6.1 + 10.25 222.22 5.55 + 10.5 308.61 6.3 + 10.75 342.6 5.6 + 11. 366. 7. + 11.25 421.3 7. + 11.5 442.55 8.3 + 11.75 506.94 9. + 12. 509.26 10.65 + 12.25 446.76 9.26 + 12.5 360.97 12.5 + 12.75 284.31 14.81 + 13. 247.36 14.81 + 13.25 256.71 15.74 + 13.5 317.13 18.98 + 13.75 337.96 20.83 + 14. 348.38 21.3 + 14.25 402.78 21.76 + 14.5 439.54 21.3 + 14.75 496.16 21.53 + 15. 490.07 24. + 15.25 434.86 18.52 + 15.5 365.74 18.5 + 15.75 328.7 17.36 + 16. 306.76 15.28 + 16.25 259.26 16.34 + 16.5 247.82 16.2 + 16.75 194.44 17.59 + 17. 157.4 17.13 + 17.25 145.97 17.6 + 17.5 102.87 18.52 + 17.75 110.79 18.5 + 18. 88.88 20. + 18.25 67.13 18.52 + 18.5 87.96 18.5 + 18.75 60.19 19.44 + 19. 39.26 19. + 19.25 13.8 19.2 + 19.5 30.37 20.83 + 19.75 34.12 21.53 + 20. 25.32 22.22 + 20.25 23.15 20.88 + 20.5 11.57 46.3 + 20.75 71.62 22. + 21. 108.8 23.15 + 21.25 111.11 23. + 21.5 118.15 23.1 + 21.75 110. 21.3 + 22. 106.48 21.76 + 22.25 94.91 24.54 + 22.5 79.49 23.15 +ENDDATA 59 +ENDSUBENT 71 +SUBENT M0816010 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (62-SM-154(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 60 +EN DATA DATA-ERR +MEV MB MB + 8. 39.31 6. + 8.25 62.43 6.47 + 8.5 87.77 6.24 + 8.75 123.1 6.71 + 9. 97.11 6.2 + 9.25 106.03 6.7 + 9.5 120.23 6.94 + 9.75 129.34 6.98 + 10. 147.65 5.78 + 10.25 200.83 6.8 + 10.5 216.23 6.84 + 10.75 240.46 6.94 + 11. 249.39 6.8 + 11.25 256.88 6.9 + 11.5 254.06 6.7 + 11.75 251.79 6.98 + 12. 247.08 7.4 + 12.25 224.64 7.49 + 12.5 212.72 10. + 12.75 187.47 9.25 + 13. 195.33 8.88 + 13.25 221.97 9.4 + 13.5 252.22 9.71 + 13.75 291.33 9.34 + 14. 321.34 10.17 + 14.25 365.32 10.4 + 14.5 401.66 9. + 14.75 386.13 + 15. 413.83 + 15.25 446.06 + 15.5 462.43 + 15.75 467.05 + 16. 469.36 + 16.25 469.41 + 16.5 445.6 + 16.75 434.68 + 17. 413.87 + 17.25 372.16 + 17.5 337.57 + 17.75 261.27 + 18. 270.43 + 18.25 226.6 + 18.5 175.72 + 18.75 122.54 + 19. 78.43 + 19.25 92.49 + 19.5 121.43 + 19.75 147.98 + 20. 147.56 + 20.25 124.2 + 20.5 97.11 + 20.75 43.94 + 21. 59.75 + 21.25 46.24 + 21.5 43.93 + 21.75 43.56 + 22. 48.55 + 22.25 39.31 + 22.5 32.37 + 22.75 41.62 +ENDDATA 62 +ENDSUBENT 72 +SUBENT M0816011 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (62-SM-154(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0816010) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 60 +EN DATA DATA-ERR +MEV MB MB + 8. 39.31 6. + 8.25 62.43 6.47 + 8.5 87.77 6.24 + 8.75 123.1 6.71 + 9. 97.11 6.2 + 9.25 106.03 6.7 + 9.5 120.23 6.94 + 9.75 129.34 6.98 + 10. 147.65 5.78 + 10.25 200.83 6.8 + 10.5 216.23 6.84 + 10.75 240.46 6.94 + 11. 249.39 6.8 + 11.25 256.88 6.9 + 11.5 254.06 6.7 + 11.75 251.79 6.98 + 12. 247.08 7.4 + 12.25 224.64 7.49 + 12.5 212.72 10. + 12.75 187.47 9.25 + 13. 195.33 8.88 + 13.25 221.97 9.4 + 13.5 252.22 9.71 + 13.75 291.33 9.34 + 14. 321.34 10.17 + 14.25 365.32 10.4 + 14.5 401.66 9. + 14.75 372.16 8.55 + 15. 349.36 9.25 + 15.25 328.33 8.79 + 15.5 308.25 9.02 + 15.75 289.57 9.11 + 16. 272.83 9.03 + 16.25 261.55 7.86 + 16.5 242.87 9.94 + 16.75 231.21 8.55 + 17. 217.34 8.32 + 17.25 191.49 9.11 + 17.5 173.27 9.24 + 17.75 131.24 8.83 + 18. 134.1 9.16 + 18.25 112.09 10.17 + 18.5 90.73 9.25 + 18.75 62.43 8.32 + 19. 41.62 9.1 + 19.25 46.24 9.25 + 19.5 66.77 10.64 + 19.75 82.73 10.17 + 20. 80.92 9.22 + 20.25 64.74 9.71 + 20.5 60.72 8.55 + 20.75 50.4 10.64 + 21. 21.92 9.25 + 21.25 27.75 9.23 + 21.5 25.2 9.34 + 21.75 22.84 9.28 + 22. 25.66 9.71 + 22.25 20.53 9.16 + 22.5 16.32 8.55 + 22.75 20.53 8.32 +ENDDATA 62 +ENDSUBENT 74 +SUBENT M0816012 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (60-ND-148(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0816003) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 23. 2406. +ENDDATA 3 +ENDSUBENT 11 +SUBENT M0816013 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (60-ND-150(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0816005) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 23. 2243. +ENDDATA 3 +ENDSUBENT 11 +SUBENT M0816014 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (62-SM-150(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0816007) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 23. 2213. +ENDDATA 3 +ENDSUBENT 11 +SUBENT M0816015 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (62-SM-152(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0816009) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 23. 3079. +ENDDATA 3 +ENDSUBENT 11 +SUBENT M0816016 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (62-SM-154(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0816011) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 23. 2478. +ENDDATA 3 +ENDSUBENT 11 +ENDENTRY 16 diff --git a/exforall/M08/M0817.x4 b/exforall/M08/M0817.x4 new file mode 100644 index 000000000..c452e56ca --- /dev/null +++ b/exforall/M08/M0817.x4 @@ -0,0 +1,1295 @@ +ENTRY M0817 20110614 20111003 20110921 M059 +SUBENT M0817001 20110614 20111003 20110921 M059 +BIB 11 25 +TITLE Giant dipole resonance on nuclei in transition region + N about 90. +AUTHOR (O.V.Vasilyev,V.A.Semenov,S.F.Semenko) +INSTITUTE (4RUSSGU) +REFERENCE (J,YF,13,463,1971) + (J,SNP,13,259,1969) + English translation of YF,13,463,1971. +FACILITY (BETAT,4RUSSGU) Saratov State University betatron + with maximum energy 25 MeV. +SAMPLE Monoisotopic oxides (X-2,O-3): + Isotope Height, g + 146Nd 2.19 + 148Sm 2.19 + 152Gd .49 + 154Gd .87 + 156Gd 2.19 + 158Gd 2.19 + 151Eu .22 + 153Eu .51 +INC-SOURCE (BRST) +DETECTOR (PROPC) 12 proportional counters. +METHOD (EXTB,SITA) +STATUS (CURVE,APRVD) Data from Fig. 2, by S.F.Semenko. +HISTORY (20110614C) Data were compiled at the Russia MSU SIMP + CDFE by V.Varlamov. +ENDBIB 25 +NOCOMMON 0 0 +ENDSUBENT 28 +SUBENT M0817002 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (60-ND-146(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 57 +EN DATA DATA-ERR +MEV MB MB + 7.75 17.07 3.66 + 8. 20.3 6.7 + 8.25 27.44 6.2 + 8.5 31.4 6.6 + 8.75 32.62 7.62 + 9. 30.79 6.8 + 9.25 45.73 6.45 + 9.5 43.11 7.32 + 9.75 48.6 3.66 + 10. 51.83 2.74 + 10.25 54.7 3. + 10.5 64.02 6.77 + 10.75 76.34 3.35 + 11. 53.53 2.13 + 11.25 85.37 1.52 + 11.5 115.86 6.7 + 11.75 110.85 3.1 + 12. 164.4 2.39 + 12.25 189.02 2.74 + 12.5 214.32 8.54 + 12.75 237.8 6.7 + 13. 277.13 7.63 + 13.25 323.17 9.76 + 13.5 339.93 10.37 + 13.75 409.57 6.77 + 14. 445.12 9.15 + 14.25 463.41 12.2 + 14.5 496.95 19.51 + 14.75 490.85 14. + 15. 451.22 13.41 + 15.25 448.17 15.24 + 15.5 390.24 24.39 + 15.75 375. 19.51 + 16. 396.34 18.29 + 16.25 311.89 18.2 + 16.5 323.17 20.3 + 16.75 268.3 9.45 + 17. 250. 18.3 + 17.25 203.23 19.21 + 17.5 161.59 18.29 + 17.75 182.93 18.2 + 18. 146.34 19. + 18.25 184.76 16. + 18.5 169.02 16.77 + 18.75 83.72 21.96 + 19. 91.1 17.8 + 19.25 33.5 33.5 + 19.75 5.37 24.63 + 20. 58. 23. + 20.25 45.73 27.44 + 20.5 46.16 30.7 + 20.75 48.78 30.79 + 21. 39.39 26.82 + 21.25 54.88 30. + 21.5 76.34 29. + 21.75 72. 31.37 + 22. 67.07 20.3 +ENDDATA 59 +ENDSUBENT 69 +SUBENT M0817003 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (60-ND-146(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0817002) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 58 +EN DATA DATA-ERR +MEV MB MB + 7.75 17.07 3.66 + 8. 20.3 6.7 + 8.25 27.44 6.2 + 8.5 31.4 6.6 + 8.75 32.62 7.62 + 9. 30.79 6.8 + 9.25 45.73 6.45 + 9.5 43.11 7.32 + 9.75 48.6 3.66 + 10. 51.83 2.74 + 10.25 54.7 3. + 10.5 64.02 6.77 + 10.75 76.34 3.35 + 11. 53.53 2.13 + 11.25 85.37 1.52 + 11.5 115.86 6.7 + 11.75 110.85 3.1 + 12. 164.4 2.39 + 12.25 189.02 2.74 + 12.5 214.32 8.54 + 12.75 237.8 6.7 + 13. 277.13 7.63 + 13.25 323.17 9.76 + 13.5 339.93 10.37 + 13.75 353.66 + 14. 329.27 + 14.25 310.98 + 14.5 307.93 + 14.75 281.46 + 15. 250. + 15.25 240.85 + 15.5 207.32 + 15.75 185.98 + 16. 203.23 + 16.25 164.53 + 16.5 164.7 + 16.75 167.5 + 17. 115.18 + 17.25 123.17 + 17.5 100. + 17.75 80.1 + 18. 91.16 + 18.25 72.62 + 18.5 91.46 + 18.75 82.32 + 19. 42.68 + 19.25 45.73 + 19.5 15.24 15.24 + 19.75 3.96 24.39 + 20. 33.54 + 20.25 24.4 + 20.5 26.83 + 20.75 24.35 + 21. 18.29 + 21.25 30. + 21.5 37.56 + 21.75 33.54 + 22. 17.8 +ENDDATA 60 +ENDSUBENT 72 +SUBENT M0817004 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (62-SM-148(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 59 +EN DATA DATA-ERR +MEV MB MB + 7.75 5.44 3.02 + 8. 6.17 2.12 + 8.25 11.55 3.33 + 8.5 18.14 3.2 + 8.75 19.37 3. + 9. 37.24 3.14 + 9.25 42. 3.62 + 9.5 48.26 5.74 + 9.75 48.19 3. + 10. 42.32 6.17 + 10.25 60.46 4.23 + 10.5 51.4 6. + 10.75 72. 3.24 + 11. 83.62 4. + 11.25 78.6 2.9 + 11.5 105.62 7.26 + 11.75 108.83 3. + 12. 136.15 3.14 + 12.25 181.38 2.6 + 12.5 199. 9.1 + 12.75 222.85 6. + 13. 266.02 3.63 + 13.25 260. 10.55 + 13.5 296.25 12.1 + 13.75 313.85 7.86 + 14. 314.39 8.52 + 14.25 326.06 5.14 + 14.5 335.85 11.6 + 14.75 365.77 12.7 + 15. 338.57 13.3 + 15.25 362.76 13.6 + 15.5 338.57 15.11 + 15.75 303.8 13.9 + 16. 350. 13.9 + 16.25 305.62 15.72 + 16.5 314.39 25.39 + 16.75 308.34 19.95 + 17. 232. 24.8 + 17.25 233.25 23. + 17.5 166.26 24.18 + 17.75 139.24 15.72 + 18. 133. 20. + 18.25 121. 21.34 + 18.5 175.33 15.72 + 18.75 160.33 15.11 + 19. 123.9 21.16 + 19.25 90.33 21.2 + 19.5 40.27 24.18 + 19.75 48.37 27.1 + 20. 113.72 27.21 + 20.25 118.46 21.6 + 20.5 123.94 21.6 + 20.75 151.15 18.74 + 21. 116.02 24.18 + 21.25 115.42 22.37 + 21.5 123.94 24.18 + 21.75 111.85 25.4 + 22. 128.23 24.2 + 22.25 145.1 24.2 +ENDDATA 61 +ENDSUBENT 71 +SUBENT M0817005 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (62-SM-148(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0817004) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 59 +EN DATA DATA-ERR +MEV MB MB + 7.75 5.44 3.02 + 8. 6.17 2.12 + 8.25 11.55 3.33 + 8.5 18.14 3.2 + 8.75 19.37 3. + 9. 37.24 3.14 + 9.25 42. 3.62 + 9.5 48.26 5.74 + 9.75 48.19 3. + 10. 42.32 6.17 + 10.25 60.46 4.23 + 10.5 51.4 6. + 10.75 72. 3.24 + 11. 83.62 4. + 11.25 78.6 2.9 + 11.5 105.62 7.26 + 11.75 108.83 3. + 12. 136.15 3.14 + 12.25 181.38 2.6 + 12.5 199. 9.1 + 12.75 222.85 6. + 13. 266.02 3.63 + 13.25 260. 10.55 + 13.5 296.25 12.1 + 13.75 313.85 7.86 + 14. 314.39 8.52 + 14.25 326.06 5.14 + 14.5 335.85 11.6 + 14.75 344.62 + 15. 278. + 15.25 268.68 + 15.5 221.46 + 15.75 187. + 16. 201.51 + 16.25 163.24 + 16.5 169.29 + 16.75 160.94 + 17. 121.04 + 17.25 120.44 + 17.5 84.64 + 17.75 67.17 + 18. 66.51 + 18.25 57.98 + 18.5 90.69 + 18.75 84.64 + 19. 62. + 19.25 48.36 + 19.5 18.14 6.71 + 19.75 18.32 + 20. 54.41 + 20.25 60.5 + 20.5 66. + 20.75 72.55 + 21. 43.35 + 21.25 63.54 + 21.5 87.12 + 21.75 42.32 + 22. 67.17 + 22.25 72. +ENDDATA 61 +ENDSUBENT 73 +SUBENT M0817006 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (64-GD-152(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 56 +EN DATA DATA-ERR +MEV MB MB + 7.5 13.34 3. + 7.75 17.12 3.3 + 8. 16.52 3.9 + 8.25 17.55 2.4 + 8.5 20. 3.33 + 8.75 29.68 3.18 + 9. 38.81 3. + 9.25 46.68 5.7 + 9.5 62.54 3.06 + 9.75 66.74 3.12 + 10. 78.09 4.81 + 10.25 90. 7.21 + 10.5 105.19 3.3 + 10.75 123.27 2.64 + 11. 143.15 4. + 11.25 156.18 7.53 + 11.5 174.21 3.06 + 11.75 204.26 5.11 + 12. 204.49 6. + 12.25 204.48 9. + 12.5 201.28 3.17 + 12.75 191.09 5.46 + 13. 183.4 5.18 + 13.25 192.23 8.89 + 13.5 231.76 5.7 + 13.75 252.29 7.5 + 14. 270.32 15. + 14.25 288.15 9.13 + 14.5 263.9 12.31 + 14.75 288.35 9.61 + 15. 314.9 15. + 15.25 297.3 15. + 15.5 330.4 13.22 + 15.75 320.48 12.31 + 16. 288.35 17.42 + 16.25 300. 21.03 + 16.5 233.56 18.62 + 16.75 188.08 19.82 + 17. 194.15 21.65 + 17.25 145.61 23.43 + 17.5 201.41 19.22 + 17.75 186.22 21. + 18. 156.19 21.02 + 18.25 192.23 20.42 + 18.5 109.21 18. + 18.75 120.14 19.83 + 19. 69.14 24. + 19.25 18.8 18.8 + 19.5 54.06 27.03 + 19.75 63.09 26.43 + 20. 69.14 27.27 + 20.25 41.81 31.24 + 20.5 46.68 19.22 + 20.75 36.04 30. + 21. 26.7 26.7 + 21.25 28.5 28.5 +ENDDATA 58 +ENDSUBENT 68 +SUBENT M0817007 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (64-GD-152(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0817006) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 56 +EN DATA DATA-ERR +MEV MB MB + 7.5 13.34 3. + 7.75 17.12 3.3 + 8. 16.52 3.9 + 8.25 17.55 2.4 + 8.5 20. 3.33 + 8.75 29.68 3.18 + 9. 38.81 3. + 9.25 46.68 5.7 + 9.5 62.54 3.06 + 9.75 66.74 3.12 + 10. 78.09 4.81 + 10.25 90. 7.21 + 10.5 105.19 3.3 + 10.75 123.27 2.64 + 11. 143.15 4. + 11.25 156.18 7.53 + 11.5 174.21 3.06 + 11.75 204.26 5.11 + 12. 204.49 6. + 12.25 204.48 9. + 12.5 201.28 3.17 + 12.75 191.09 5.46 + 13. 183.4 5.18 + 13.25 192.23 8.89 + 13.5 231.76 5.7 + 13.75 252.29 7.5 + 14. 270.32 15. + 14.25 288.15 9.13 + 14.5 263.9 12.31 + 14.75 288.35 9.61 + 15. 312.37 + 15.25 245.94 + 15.5 237.46 + 15.75 218.42 + 16. 177.33 + 16.25 173.5 + 16.5 131.62 + 16.75 107.96 + 17. 107.94 + 17.25 80.2 + 17.5 102.94 + 17.75 96.12 + 18. 80. + 18.25 100. + 18.5 60. + 18.75 63.14 + 19. 38.8 + 19.25 9. + 19.5 29. + 19.75 40. + 20. 40.55 + 20.25 23.6 + 20.5 29.07 + 20.75 18.02 + 21. 11.47 + 21.25 13.34 +ENDDATA 58 +ENDSUBENT 70 +SUBENT M0817008 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (64-GD-154(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 58 +EN DATA DATA-ERR +MEV MB MB + 7.75 12.12 3.24 + 8. 12.24 3.64 + 8.25 9.15 4.55 + 8.5 13.45 5.45 + 8.75 15.27 4.5 + 9. 30. 6. + 9.25 40. 2.73 + 9.5 50.18 6.06 + 9.75 60.61 3.03 + 10. 71.58 9. + 10.25 87.52 4.85 + 10.5 88.12 6.67 + 10.75 111.4 5.15 + 11. 127.27 9.1 + 11.25 148.48 5.45 + 11.5 169.7 6.1 + 11.75 196.97 9.15 + 12. 214.24 6.7 + 12.25 220.36 5.45 + 12.5 227.27 8.48 + 12.75 206.06 6.73 + 13. 181.33 6. + 13.25 177.52 7.27 + 13.5 189.76 6.97 + 13.75 212.12 6.36 + 14. 242.42 8.55 + 14.25 266.67 11.52 + 14.5 276. 9.15 + 14.75 267.52 9.7 + 15. 281.58 10.3 + 15.25 260.12 9.1 + 15.5 278.79 12.12 + 15.75 300. 12.73 + 16. 309.1 13.33 + 16.25 324.42 13.35 + 16.5 263.21 15.16 + 16.75 244.85 16.36 + 17. 220.36 19.4 + 17.25 208.12 17.69 + 17.5 260.61 18.18 + 17.75 236.36 18.2 + 18. 193.94 17.88 + 18.25 146.91 15.27 + 18.5 120.67 18. + 18.75 96.97 17.76 + 19. 74. 15.27 + 19.25 78.79 19.58 + 19.5 33.64 19.55 + 19.75 78.79 18.2 + 20. 151.52 20. + 20.25 160.61 20.19 + 20.5 180.73 21.21 + 20.75 145. 27. + 21. 100.7 27.33 + 21.25 54.54 24.48 + 21.5 72.72 25.7 + 21.75 33.64 26.06 + 22. 45.88 36.36 +ENDDATA 60 +ENDSUBENT 70 +SUBENT M0817009 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (64-GD-154(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0817008) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 58 +EN DATA DATA-ERR +MEV MB MB + 7.75 12.12 3.24 + 8. 12.24 3.64 + 8.25 9.15 4.55 + 8.5 13.45 5.45 + 8.75 15.27 4.5 + 9. 30. 6. + 9.25 40. 2.73 + 9.5 50.18 6.06 + 9.75 60.61 3.03 + 10. 71.58 9. + 10.25 87.52 4.85 + 10.5 88.12 6.67 + 10.75 111.4 5.15 + 11. 127.27 9.1 + 11.25 148.48 5.45 + 11.5 169.7 6.1 + 11.75 196.97 9.15 + 12. 214.24 6.7 + 12.25 220.36 5.45 + 12.5 227.27 8.48 + 12.75 206.06 6.73 + 13. 181.33 6. + 13.25 177.52 7.27 + 13.5 189.76 6.97 + 13.75 212.12 6.36 + 14. 242.42 8.55 + 14.25 266.67 11.52 + 14.5 276. 9.15 + 14.75 267.52 9.7 + 15. 281.58 10.3 + 15.25 260.12 9.1 + 15.5 245.45 + 15.75 230.3 + 16. 214.24 + 16.25 202. + 16.5 154.7 + 16.75 140.79 + 17. 118.24 + 17.25 91.82 + 17.5 134.7 + 17.75 121.21 + 18. 102.8 + 18.25 75.88 + 18.5 58.12 + 18.75 48.48 + 19. 40.36 + 19.25 37.33 + 19.5 20.28 + 19.75 40. + 20. 75.9 + 20.25 84.8 + 20.5 91.82 + 20.75 72.72 + 21. 48.5 + 21.25 26.91 + 21.5 36.36 + 21.75 18.18 + 22. 24.24 +ENDDATA 60 +ENDSUBENT 72 +SUBENT M0817010 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (64-GD-156(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 56 +EN DATA DATA-ERR +MEV MB MB + 7.75 6.15 6. + 8. 9.28 6. + 8.25 17.34 6.14 + 8.5 27.9 6.2 + 8.75 40.94 6.27 + 9. 55.2 6.84 + 9.25 61.48 6.45 + 9.5 73.22 5.84 + 9.75 78.2 5.53 + 10. 85.64 5.23 + 10.25 107.58 6.82 + 10.5 141.39 4.3 + 10.75 159.84 5.72 + 11. 181.29 5.84 + 11.25 202.38 8.18 + 11.5 193.22 6.82 + 11.75 209.02 5.9 + 12. 227.03 6.75 + 12.25 200. 8.6 + 12.5 226.41 6.45 + 12.75 208.59 6.15 + 13. 190.58 3. + 13.25 219.16 8.6 + 13.5 183.93 7.07 + 13.75 202.87 9.22 + 14. 228.26 9.84 + 14.25 231.95 12.42 + 14.5 289. 9.74 + 14.75 288.9 9.41 + 15. 310.76 11.8 + 15.25 334.73 14.14 + 15.5 350.84 12.42 + 15.75 341.5 13.65 + 16. 335.29 14.75 + 16.25 291.82 17.83 + 16.5 223.52 20.29 + 16.75 273.81 19. + 17. 221.31 21.52 + 17.25 242.83 22.13 + 17.5 223.52 20.29 + 17.75 166. 13.83 + 18. 150.86 19.67 + 18.25 113.73 24.6 + 18.5 153.32 22.32 + 18.75 58.4 20.47 + 19. 70.76 24.84 + 19.25 162.9 24.59 + 19.5 55.33 15.37 + 19.75 214.73 19.67 + 20. 186.27 24.6 + 20.25 50.9 26.43 + 20.5 141.39 24.6 + 20.75 17. 17. + 21. 21.5 21.5 + 21.25 27.3 27.3 + 21.5 24.6 24.6 +ENDDATA 58 +ENDSUBENT 68 +SUBENT M0817011 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (64-GD-156(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0817010) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 56 +EN DATA DATA-ERR +MEV MB MB + 7.75 6.15 6. + 8. 9.28 6. + 8.25 17.34 6.14 + 8.5 27.9 6.2 + 8.75 40.94 6.27 + 9. 55.2 6.84 + 9.25 61.48 6.45 + 9.5 73.22 5.84 + 9.75 78.2 5.53 + 10. 85.64 5.23 + 10.25 107.58 6.82 + 10.5 141.39 4.3 + 10.75 159.84 5.72 + 11. 181.29 5.84 + 11.25 202.38 8.18 + 11.5 193.22 6.82 + 11.75 209.02 5.9 + 12. 227.03 6.75 + 12.25 200. 8.6 + 12.5 226.41 6.45 + 12.75 208.59 6.15 + 13. 190.58 3. + 13.25 219.16 8.6 + 13.5 183.93 7.07 + 13.75 202.87 9.22 + 14. 228.26 9.84 + 14.25 231.95 12.42 + 14.5 289. 9.74 + 14.75 288.9 9.41 + 15. 298.16 + 15.25 279.4 + 15.5 258.2 + 15.75 225.18 + 16. 202.87 + 16.25 169.06 + 16.5 126.02 + 16.75 156.89 + 17. 116.8 + 17.25 125.53 + 17.5 116.8 + 17.75 66.45 + 18. 76.97 + 18.25 55.33 + 18.5 76.35 + 18.75 30.37 + 19. 36.89 + 19.25 60.55 + 19.5 25.45 + 19.75 101.43 + 20. 92.21 + 20.25 21.52 + 20.5 65.23 + 20.75 5.5 + 21. 5.8 + 21.25 6.8 + 21.5 12. +ENDDATA 58 +ENDSUBENT 70 +SUBENT M0817012 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (64-GD-158(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 59 +EN DATA DATA-ERR +MEV MB MB + 7.75 9. 4. + 8. 18.23 4.81 + 8.25 24.06 3.33 + 8.5 30. 3. + 8.75 38.86 3.61 + 9. 48.12 9. + 9.25 49.2 3.65 + 9.5 60. 7.22 + 9.75 66.17 6. + 10. 72.18 5.71 + 10.25 99.61 4.51 + 10.5 115.43 7.2 + 10.75 138.35 6. + 11. 159.52 7.5 + 11.25 171.49 5.41 + 11.5 186.47 9. + 11.75 213.83 6.32 + 12. 235. 6.68 + 12.25 234.57 6.62 + 12.5 240.84 9.62 + 12.75 198.5 7.82 + 13. 177.38 7.7 + 13.25 186.47 12. + 13.5 170.1 12.1 + 13.75 197.47 9.92 + 14. 240.6 9. + 14.25 251.23 11.4 + 14.5 295.34 13.23 + 14.75 355.43 14.44 + 15. 360. 14.5 + 15.25 378.47 15. + 15.5 391. 16.24 + 15.75 367. 18.71 + 16. 378.95 21. + 16.25 388.2 21.11 + 16.5 334.14 27. + 16.75 312.24 27.4 + 17. 276.7 25.86 + 17.25 213.53 27.07 + 17.5 237.6 24. + 17.75 204. 22. + 18. 216.54 21.65 + 18.25 217.5 20. + 18.5 117.35 24.1 + 18.75 120.3 21.65 + 19. 40. 20. + 19.25 45.11 22.55 + 19.5 131.85 29.5 + 19.75 137.86 21. + 20. 165.41 30.07 + 20.25 132.33 25.26 + 20.5 78.2 29. + 20.75 57. 24. + 21. 57.14 22.86 + 21.25 114.29 26.47 + 21.5 77.11 27.12 + 21.75 90.23 33. + 22. 86.68 25.56 + 22.25 95.94 26.7 +ENDDATA 61 +ENDSUBENT 71 +SUBENT M0817013 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (64-GD-158(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0817012) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 59 +EN DATA DATA-ERR +MEV MB MB + 7.75 9. 4. + 8. 18.23 4.81 + 8.25 24.06 3.33 + 8.5 30. 3. + 8.75 38.86 3.61 + 9. 48.12 9. + 9.25 49.2 3.65 + 9.5 60. 7.22 + 9.75 66.17 6. + 10. 72.18 5.71 + 10.25 99.61 4.51 + 10.5 115.43 7.2 + 10.75 138.35 6. + 11. 159.52 7.5 + 11.25 171.49 5.41 + 11.5 186.47 9. + 11.75 213.83 6.32 + 12. 235. 6.68 + 12.25 234.57 6.62 + 12.5 240.84 9.62 + 12.75 198.5 7.82 + 13. 177.38 7.7 + 13.25 186.47 12. + 13.5 170.1 12.1 + 13.75 197.47 9.92 + 14. 240.6 9. + 14.25 251.23 11.4 + 14.5 295.34 13.23 + 14.75 303.46 + 15. 270.68 + 15.25 252.63 + 15.5 240.6 + 15.75 220.33 + 16. 213.71 + 16.25 210.53 + 16.5 177.44 + 16.75 163.13 + 17. 131.79 + 17.25 112.36 + 17.5 120.3 + 17.75 102.02 + 18. 111.28 + 18.25 108.27 + 18.5 60.15 + 18.75 63.22 + 19. 20. + 19.25 26.7 + 19.5 62.62 + 19.75 71.64 + 20. 86.68 + 20.25 69.23 + 20.5 36.1 + 20.75 26.71 + 21. 30. + 21.25 60. + 21.5 33.38 + 21.75 51.6 + 22. 43.13 + 22.25 51. +ENDDATA 61 +ENDSUBENT 73 +SUBENT M0817014 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (63-EU-151(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 57 +EN DATA DATA-ERR +MEV MB MB + 7.75 5.4 5.4 + 8. 12.09 4.8 + 8.25 11.55 4.54 + 8.5 20. 5.44 + 8.75 21.34 6. + 9. 24.18 3.33 + 9.25 30.23 3.63 + 9.5 36. 6. + 9.75 45.34 3. + 10. 48.85 5.44 + 10.25 56.17 4.53 + 10.5 69.59 6.1 + 10.75 69.53 4.84 + 11. 89.9 4.84 + 11.25 102.78 4.53 + 11.5 108.83 6.66 + 11.75 142.26 7.38 + 12. 157.2 9. + 12.25 170.98 7.7 + 12.5 181.38 9.67 + 12.75 205.56 8.46 + 13. 217.65 7.38 + 13.25 238.81 9. + 13.5 259.61 9. + 13.75 269.29 6.71 + 14. 287.24 9.1 + 14.25 296.25 8.79 + 14.5 305.32 7.2 + 14.75 299.21 12. + 15. 232.95 15.11 + 15.25 329.5 15. + 15.5 338.57 20.7 + 15.75 344.62 25.7 + 16. 435.3 21.16 + 16.25 262.58 18.74 + 16.5 202.72 20.15 + 16.75 220.68 21.16 + 17. 146.55 19.65 + 17.25 235.8 21.77 + 17.5 241.41 21.16 + 17.75 150.79 25.39 + 18. 181.56 21.77 + 18.25 114.87 30.23 + 18.5 140.46 29.92 + 18.75 140.44 30.53 + 19. 75.7 26. + 19.25 81.8 24.18 + 19.5 136.15 41.11 + 19.75 85.49 30.83 + 20. 154.29 36.64 + 20.25 169.29 39.3 + 20.5 122.13 37.48 + 20.75 219.83 38. + 21. 164.87 33.55 + 21.25 201.51 39.3 + 21.5 211.61 39.3 + 21.75 213.72 39.3 +ENDDATA 59 +ENDSUBENT 69 +SUBENT M0817015 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (63-EU-151(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0817014) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 57 +EN DATA DATA-ERR +MEV MB MB + 7.75 5.4 5.4 + 8. 12.09 4.8 + 8.25 11.55 4.54 + 8.5 20. 5.44 + 8.75 21.34 6. + 9. 24.18 3.33 + 9.25 30.23 3.63 + 9.5 36. 6. + 9.75 45.34 3. + 10. 48.85 5.44 + 10.25 56.17 4.53 + 10.5 69.59 6.1 + 10.75 69.53 4.84 + 11. 89.9 4.84 + 11.25 102.78 4.53 + 11.5 108.83 6.66 + 11.75 142.26 7.38 + 12. 157.2 9. + 12.25 170.98 7.7 + 12.5 181.38 9.67 + 12.75 205.56 8.46 + 13. 217.65 7.38 + 13.25 238.81 9. + 13.5 259.61 9. + 13.75 269.29 6.71 + 14. 287.24 9.1 + 14.25 296.25 8.79 + 14.5 305.32 7.2 + 14.75 274.79 + 15. 187.42 + 15.25 232.77 + 15.5 217.65 + 15.75 205.56 + 16. 247.52 + 16.25 146.55 + 16.5 108.83 + 16.75 118. + 17. 78.6 + 17.25 121.04 + 17.5 120.92 + 17.75 73.82 + 18. 90.69 + 18.25 57.44 + 18.5 54.96 + 18.75 73.82 + 19. 37.24 + 19.25 43.95 + 19.5 66.51 + 19.75 45.34 + 20. 78.6 + 20.25 87.12 + 20.5 66.5 + 20.75 105.86 + 21. 84.22 + 21.25 102.78 + 21.5 108.83 + 21.75 106.23 +ENDDATA 59 +ENDSUBENT 71 +SUBENT M0817016 20110614 20111003 20110921 M059 +BIB 3 5 +REACTION (63-EU-153(G,X)0-NN-1,,SIG,,BRS) +ANALYSIS (UNFLD,PLA) Penfold-Leiss method with step 1 MeV for + cross section unfolding from experimental yield + curve. +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 5 +NOCOMMON 0 0 +DATA 3 57 +EN DATA DATA-ERR +MEV MB MB + 8.25 6. 6. + 8.5 11.58 6.66 + 8.75 17.7 4.24 + 9. 26.9 3.33 + 9.25 42.42 4.55 + 9.5 51.51 6.06 + 9.75 60.61 3.64 + 10. 72.73 5.44 + 10.25 103.03 5.46 + 10.5 96.97 6.12 + 10.75 115.15 7.27 + 11. 139.39 4.84 + 11.25 126.78 4.53 + 11.5 186.66 7.26 + 11.75 190.09 6.1 + 12. 200. 6.73 + 12.25 236.36 5.57 + 12.5 175.28 8.17 + 12.75 189.75 6.06 + 13. 181.82 7.28 + 13.25 132.78 4. + 13.5 193.94 12.12 + 13.75 197.19 7.81 + 14. 205.64 9.1 + 14.25 254.55 12.09 + 14.5 248.48 13.94 + 14.75 245.45 10.91 + 15. 276. 12.24 + 15.25 296.97 15.75 + 15.5 284.84 17.75 + 15.75 348.48 15.75 + 16. 342.78 15.15 + 16.25 318.18 16.97 + 16.5 321.21 23. + 16.75 269.33 26.91 + 17. 230.33 25.45 + 17.25 230.3 23.64 + 17.5 206.06 24.24 + 17.75 178.78 21.82 + 18. 181.82 24.2 + 18.25 175.76 20. + 18.5 145. 21.21 + 18.75 140. 21.52 + 19. 121.21 23. + 19.25 90.9 21.21 + 19.5 103.03 21.3 + 19.75 102.79 23.33 + 20. 91.82 26.67 + 20.25 110.18 23.64 + 20.5 75.75 30. + 20.75 72.72 32. + 21. 109.1 30.9 + 21.25 100. 31.82 + 21.5 72.72 33.33 + 21.75 103.03 30.3 + 22. 63.7 24.24 + 22.25 84.85 27.27 +ENDDATA 59 +ENDSUBENT 69 +SUBENT M0817017 20110614 20111003 20110921 M059 +BIB 4 7 +REACTION (63-EU-153(G,X)0-NN-1,UNW,SIG,,BRS,DERIV) +ANALYSIS The (g,sn) = (g,n) + (g,2n) + ... reaction cross + section was obtained from the (g,xn) reaction + cross section unfolded from reaction yield measured + using statistical theory. +STATUS (DEP,M0817016) +ERR-ANALYS (DATA-ERR) Root-mean-squared errors. +ENDBIB 7 +NOCOMMON 0 0 +DATA 3 57 +EN DATA DATA-ERR +MEV MB MB + 8.25 6. 6. + 8.5 11.58 6.66 + 8.75 17.7 4.24 + 9. 26.9 3.33 + 9.25 42.42 4.55 + 9.5 51.51 6.06 + 9.75 60.61 3.64 + 10. 72.73 5.44 + 10.25 103.03 5.46 + 10.5 96.97 6.12 + 10.75 115.15 7.27 + 11. 139.39 4.84 + 11.25 126.78 4.53 + 11.5 186.66 7.26 + 11.75 190.09 6.1 + 12. 200. 6.73 + 12.25 236.36 5.57 + 12.5 175.28 8.17 + 12.75 189.75 6.06 + 13. 181.82 7.28 + 13.25 132.78 4. + 13.5 193.94 12.12 + 13.75 197.19 7.81 + 14. 205.64 9.1 + 14.25 254.55 12.09 + 14.5 248.48 13.94 + 14.75 245.45 10.91 + 15. 276. 12.24 + 15.25 266.67 + 15.5 224.24 + 15.75 236.36 + 16. 215.33 + 16.25 187.87 + 16.5 184.85 + 16.75 148.48 + 17. 117.88 + 17.25 115.15 + 17.5 109.1 + 17.75 94.24 + 18. 93.64 + 18.25 87.52 + 18.5 72.73 + 18.75 71.64 + 19. 64.12 + 19.25 48.48 + 19.5 55.15 + 19.75 55.45 + 20. 48.97 + 20.25 60. + 20.5 45.45 + 20.75 41.21 + 21. 52. + 21.25 48.48 + 21.5 40.36 + 21.75 54.54 + 22. 33.03 + 22.25 48.48 +ENDDATA 59 +ENDSUBENT 71 +SUBENT M0817018 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (60-ND-146(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0817003) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 22. 2120. +ENDDATA 3 +ENDSUBENT 11 +SUBENT M0817019 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (62-SM-148(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0817005) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 22. 2080. +ENDDATA 3 +ENDSUBENT 11 +SUBENT M0817020 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (64-GD-152(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0817007) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 22. 1990. +ENDDATA 3 +ENDSUBENT 11 +SUBENT M0817021 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (64-GD-154(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0817009) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 22. 2000. +ENDDATA 3 +ENDSUBENT 11 +SUBENT M0817022 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (64-GD-156(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0817011) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 22. 2110. +ENDDATA 3 +ENDSUBENT 11 +SUBENT M0817023 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (64-GD-158(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0817013) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 22. 2160. +ENDDATA 3 +ENDSUBENT 11 +SUBENT M0817024 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (63-EU-151(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0817015) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 22. 2020. +ENDDATA 3 +ENDSUBENT 11 +SUBENT M0817025 20110614 20111003 20110921 M059 +BIB 3 3 +REACTION (63-EU-153(G,X)0-NN-1,UNW,INT,,BRA) +ERR-ANALYS No information. +STATUS (DEP,M0817017) Excitation function. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 1 +EN-MAX DATA +MEV MB*MEV + 22. 1900. +ENDDATA 3 +ENDSUBENT 11 +ENDENTRY 25 diff --git a/exforall/M08/M0818.x4 b/exforall/M08/M0818.x4 new file mode 100644 index 000000000..897242ec8 --- /dev/null +++ b/exforall/M08/M0818.x4 @@ -0,0 +1,55 @@ +ENTRY M0818 20110621 20111003 20110921 M059 +SUBENT M0818001 20110621 20111003 20110921 M059 +BIB 11 16 +TITLE Integrated cross sections for 209Bi(gamma,xnyp) + reactions. +REFERENCE (J,PR,159,953,1967) + #doi:10.1103/PhysRev.159.953 +INSTITUTE (1USANIS) +AUTHOR (J.M.Wyckoff) +FACILITY (LINAC,1USANBS) +INC-SOURCE (BRST) Bremsstrahlung with end-point energy 137 MeV. +DETECTOR (GELI) High-resolution Ge(Li) g-ray spectrometer. +SAMPLE Natural bismuth target. +ERR-ANALYS (DATA-ERR) Uncertainties were deduced from the + scatter of the yield points and thick target + bremsstrahlung shape uncertainty. +STATUS (TABLE) Data from the Table 1 were compiled at the + Russia MSU SINP CDFE by V.Varlamov. +HISTORY (20110621C) +ENDBIB 16 +NOCOMMON 0 0 +ENDSUBENT 19 +SUBENT M0818002 20110621 20111003 20110921 M059 +BIB 3 5 +REACTION (83-BI-209(G,X)ELEM/MASS,,INT,,BRA) +FLAG (1.) Data used for normalization. +REL-REF (R,L0007013,R.R.HARVEY+,J,PR,136,B126,1964) Data for + (g,2n) reaction cross section used for + normalization. +ENDBIB 5 +COMMON 1 3 +EN-MAX +MEV + 137. +ENDCOMMON 3 +DATA 5 14 +ELEMENT MASS DATA DATA-ERR FLAG +NO-DIM NO-DIM MB*MEV MB*MEV NO-DIM + 83. 208. 2170. 1. + 83. 207. 760. 38. 1. + 83. 206. 168. 35. + 83. 205. 88. 22. + 83. 204. 55. 16. + 83. 203. 66. 23. + 83. 202. 31. 12. + 83. 201. 10.7 5.9 + 83. 200. 5.7 3.4 + 82. 204. 8. 2.4 + 82. 203. 3.8 1.3 + 82. 202. 3.4 1.3 + 82. 201. 15.3 8.4 + 82. 200. 1.62 .97 +ENDDATA 16 +ENDSUBENT 30 +ENDENTRY 2 diff --git a/exforall/M08/M0819.x4 b/exforall/M08/M0819.x4 new file mode 100644 index 000000000..6ade56882 --- /dev/null +++ b/exforall/M08/M0819.x4 @@ -0,0 +1,66 @@ +ENTRY M0819 20110622 20111003 20110921 M059 +SUBENT M0819001 20110622 20111003 20110921 M059 +BIB 12 24 +TITLE Elastic scattering of 11.5 - 17.7 MeV photons by Au + measured with a bremsstrahlung monochromator. +AUTHOR (J.S.O'Connell,P.A.Tipler,P.Axel) +REFERENCE (J,PR,126,228,1962) + #doi:10.1103/PhysRev.126.228 +INSTITUTE (1USAUI) +FACILITY (BETAT,1USAUI) +INC-SOURCE (MPH,TAGD) Monochromatic photons from bremsstrahlung + tagging monochromator. +DETECTOR (NAICR) +SAMPLE 197Au target. +ANALYSIS Elastic scattering cross section obtained directly + by measuring the number of scattered gamma rays for + a recorded number of electrons of definite energy. +ERR-ANALYS (ERR-S) Statistical errors. There might be additional + errors: + (ERR-1) unknown fluctuations in Nt/Ne (where Nt is a + number of true counts and Ne is number of energy + degraded electrons) that is about 10 %, + and + (ERR-2) 10 % in the absolute cross section. +STATUS (TABLE) Data from the Table 1 (and Fig. 6) were + compiled at the Russia MSU SINP CDFE by V.Varlamov. +HISTORY (20110622C) +ENDBIB 24 +COMMON 4 3 +ANG EN-RSL ERR-1 ERR-2 +ADEG PER-CENT PER-CENT PER-CENT + 135. 2.14 10. 10. +ENDCOMMON 3 +ENDSUBENT 31 +SUBENT M0819002 20110622 20111003 20110921 M059 +BIB 1 1 +REACTION (79-AU-197(G,EL)79-AU-197,,DA) +ENDBIB 1 +NOCOMMON 0 0 +DATA 3 21 +EN DATA ERR-S +MEV MB/SR MB/SR + 11.48 .08 .045 + 11.66 .141 .058 + 11.84 .1 .05 + 12.5 .302 .066 + 12.64 .294 .079 + 12.78 .357 .073 + 13.3 .614 .11 + 13.45 .583 .12 + 13.62 .821 .14 + 14.3 .72 .08 + 14.44 .818 .097 + 14.58 .599 .087 + 15.29 .611 .011 + 15.41 .58 .12 + 15.53 .445 .11 + 16.55 .43 .13 + 16.69 .359 .15 + 16.83 .359 .14 + 17.48 .108 .105 + 17.6 .359 .135 + 17.72 .578 .17 +ENDDATA 23 +ENDSUBENT 29 +ENDENTRY 2 diff --git a/exforall/M08/M0820.x4 b/exforall/M08/M0820.x4 new file mode 100644 index 000000000..363271f7a --- /dev/null +++ b/exforall/M08/M0820.x4 @@ -0,0 +1,69 @@ +ENTRY M0820 20110622 20111003 20110921 M059 +SUBENT M0820001 20110622 20111003 20110921 M059 +BIB 14 21 +TITLE Nuclear Raman scattering of 10.83 MeV photons by + 238U, 232Th, and 209Bi. +CRITIQUE In the title of article photon energy is nominated as + 10.38 MeV. + Only data for uranium are presented. +AUTHOR (H.E.JACKSON,K.J.WETZEL) +REFERENCE (J,PRL,28,513,1972) + #doi:10.1103/PhysRevLett.28.513 +INSTITUTE (1USAUI) +FACILITY (REAC,1USAUI) +INC-SOURCE (MPH=(7-N-14(N,G)7-N-15)) 350 g height melamine + (C-3,H-6,N-6) target at the core of CP-5 reactor. +SAMPLE No information. +ERR-ANALYS No information. +REL-REF (I,,H.E.JACKSON+,J,PRL,22,1008,1969) + More details of experimental method. +METHOD (EXTB) +DETECTOR (GELI) Ge(Li) detector with an energy resolution of + 10 keV for 10 MeV. +STATUS (TABLE) Data are published in text (Fig. 2) +HISTORY (20110622C) +ENDBIB 21 +COMMON 1 3 +EN +MEV + 10.83 +ENDCOMMON 3 +ENDSUBENT 28 +SUBENT M0820002 20110622 20111003 20110921 M059 +BIB 1 1 +REACTION (92-U-238(G,EL)92-U-238,,DA) +ENDBIB 1 +NOCOMMON 0 0 +DATA 3 7 +ANG DATA DATA-ERR +ADEG MB/SR MB/SR + 20. 1.72 .17 + 30. .97 .12 + 50. .43 .05 + 70. .31 .03 + 90. .23 .02 + 120. .25 .02 + 150. .39 .04 +ENDDATA 9 +ENDSUBENT 15 +SUBENT M0820003 20110622 20111003 20110921 M059 +BIB 2 3 +REACTION (92-U-238(G,INL)92-U-238,PAR,DA) +EN-SEC (E-LVL,92-U-238) 2+ excited state for the inelastic + scattering. +ENDBIB 3 +COMMON 1 3 +E-LVL +KEV +45. +ENDCOMMON 3 +DATA 3 4 +ANG DATA DATA-ERR +ADEG MB/SR MB/SR + 70. .18 .02 + 90. .2 .02 +120. .21 .02 +150. .2 .02 +ENDDATA 6 +ENDSUBENT 18 +ENDENTRY 3 diff --git a/exforall/M08/M0821.x4 b/exforall/M08/M0821.x4 new file mode 100644 index 000000000..92d2b341d --- /dev/null +++ b/exforall/M08/M0821.x4 @@ -0,0 +1,261 @@ +ENTRY M0821 20110622 20111003 20110921 M059 +SUBENT M0821001 20110622 20111003 20110921 M059 +BIB 12 31 +TITLE The photoresponse of stable N = 82 nuclei below 10 + MeV. +AUTHOR (S.Volz,N.Tsoneva,M.Babilon,M.Elvers,J.Hasper, + R.-D.Herzberg,H.Lenske,K.Lindenberg,D.Savran, + A.Zilges) +REFERENCE (J,NP/A,779,1,2006) + #doi:10.1016/j.nuclphysa.2006.08.012 +INSTITUTE (2GERTHD,2GERJLU,3BULBLA,2UK LVP) +FACILITY (LINAC,2GERTHD) Superconducting linear electron + accelerator S-DALINAC at Darmstadt University of + Technology (TU Darmstadt). +INC-SOURCE (BRST) Bremsstrahlung facility with end-point energy + 6.8 MeV. +SAMPLE Targets consist typically of 1 - 3 g of isotopically + enriched material: + Target Enrichment, Mass, Neutron + % mg separation energy, MeV + (138Ba-2)CO-3 99.5 3011 8.6 + 140CeO-2 88.5 3160 9.2 + (142Nd-2)O-3 95.7 865 9.8 + (144Sm-2)O-3 96.5 726 10.5 +DETECTOR (HPGE) Two high-purity germanium detectors with + efficiences of 100 % relative to a standard NaI + detector (a cylinder with a length of 7.62 cm and a + diameter of 7.62 mm), positioned at 90 and 130 + degree relative to the incoming photon beam. +METHOD (GSPEC) +ERR-ANALYS (DATA-ERR) No information. +STATUS (TABLE) Data from Tables 2 - 5 were compiled at the + Russia MSU SINP CDFE by V.Varlamov. +HISTORY (20110622C) +ENDBIB 31 +NOCOMMON 0 0 +ENDSUBENT 34 +SUBENT M0821002 20110622 20111003 20110921 M059 +BIB 2 5 +REACTION 1(56-BA-138(G,0),,EN) Excitation energy Ex. + 2((56-BA-138(G,EL),,WID,,SQ)/(56-BA-138(G,TOT),,WID)) +CRITIQUE Authors say (page 7, 10-th line from the top) that + integrated cross sections I-0 are presented in the + Table 2 but that is not in case. +ENDBIB 5 +NOCOMMON 0 0 +DATA 4 63 +DATA 1DATA-ERR 1DATA 2DATA-ERR 2 +KEV KEV NO-DIM NO-DIM + 4025.6 .5 394. 60. + 4323. .7 101. 18. + 4535.1 .6 183. 31. + 4705.6 .9 61. 14. + 4854.7 1.4 521. 80. + 5145.4 .6 541. 85. + 5283.9 .7 276. 45. + 5390.7 .6 660. 124. + 5475.7 .6 316. 52. + 5511.3 1. 1918. 290. + 5582.1 .7 333. 55. + 5644.6 .5 1528. 242. + 5655.3 .7 542. 113. + 5694.5 .7 354. 60. + 5742.9 .7 432. 70. + 5766.3 .6 578. 93. + 5815. .7 419. 71. + 5873.6 .6 1036. 160. + 5963.5 .6 824. 130. + 6102.2 .7 1049. 600. + 6114.5 .9 629. 185. + 6192.9 .5 1775. 271. + 6244.6 .8 558. 92. + 6347.9 .8 809. 129. + 6361.6 .6 1310. 203. + 6410.1 .6 2366. 363. + 6434.3 .6 2301. 353. + 6465.8 .7 603. 104. + 6486.3 .9 246. 54. + 6552.6 .8 614. 108. + 6557.3 .8 687. 120. + 6612.7 .6 2758. 424. + 6635.1 .8 484. 91. + 6663.7 .7 730. 121. + 6678.6 .5 2565. 393. + 6693.4 .5 2717. 415. + 6703.5 .6 1059. 170. + 6801.9 .8 622. 110. + 6813.4 .6 2247. 352. + 6821.6 1.1 457. 100. + 6839.1 .8 697. 122. + 6848.3 .7 1366. 217. + 6862. .6 1767. 278. + 6870.4 .7 1146. 186. + 6894.8 .6 2790. 428. + 6922.1 .8 1096. 182. + 6966.8 1.2 734. 154. + 6980.9 .8 616. 111. + 7040.1 .9 566. 105. + 7105.9 1.5 604. 111. + 7143.8 .9 471. 95. + 7211.6 .8 1673. 268. + 7275.8 1. 2481. 399. + 7334.1 1. 894. 160. + 7376.6 .9 1029. 180. + 7546.7 2.2 608. 135. + 7705.6 1.2 1207. 222. + 7774. .7 2328. 376. + 7805.3 .8 1368. 239. + 7819.7 .8 1469. 256. + 7871.1 1. 1415. 267. + 8075.6 .8 2996. 490. + 8433.2 1.4 871. 230. +ENDDATA 65 +ENDSUBENT 75 +SUBENT M0821003 20110622 20111003 20110921 M059 +BIB 1 2 +REACTION 1(58-CE-140(G,0),,EN) Excitation energy Ex. + 2(58-CE-140(G,EL),,WID/STR,,MSC) +ENDBIB 2 +NOCOMMON 0 0 +DATA 4 42 +DATA 1DATA-ERR 1DATA 2DATA-ERR 2 +KEV KEV MILLI-EV MILLI-EV + 3643.8 .6 367. 56. + 4173.6 .8 128. 25. + 4354.9 .7 122. 26. + 4514.9 .9 168. 31. + 4787.8 .9 199. 38. + 5157.3 1.2 177. 31. + 5190.2 1. 222. 46. + 5211.6 1.4 132. 35. + 5337.3 .9 253. 51. + 5548.4 .7 470. 80. + 5573.8 1.4 271. 59. + 5659.9 .6 1646. 254. + 5928.6 1. 391. 80. + 6119.1 1.5 655. 112. + 6130.6 1.2 302. 62. + 6161.7 1.4 421. 97. + 6273.6 1. 434. 81. + 6295.3 .8 989. 176. + 6327.8 1.2 350. 129. + 6343.3 1.1 583. 113. + 6352.7 1. 664. 123. + 6397.2 .8 1588. 257. + 6439.9 1.4 852. 146. + 6449.9 1.5 502. 99. + 6458.5 1.5 454. 94. + 6484.8 1. 447. 91. + 6497. .7 1370. 228. + 6535.8 .6 2059. 321. + 6549.1 1.1 358. 75. + 6574.9 1.5 392. 77. + 6605. 1. 658. 113. + 6616.2 1. 610. 106. + 6781.9 1.5 531. 116. + 6841.8 1.2 575. 158. + 6862.4 .7 1863. 321. + 6905.9 1.5 1009. 220. + 6932.6 1.4 876. 189. + 6960.4 1.2 962. 199. + 7206. 1.4 1434. 244. + 7214.8 1.5 1322. 227. + 7341.5 1.4 507. 197. + 7673.4 1.2 599. 140. +ENDDATA 44 +ENDSUBENT 51 +SUBENT M0821004 20110622 20111003 20110921 M059 +BIB 1 2 +REACTION 1(60-ND-142(G,0),,EN) Excitation energy Ex. + 2(60-ND-142(G,EL),,WID/STR,,MSC) +ENDBIB 2 +NOCOMMON 0 0 +DATA 4 42 +DATA 1DATA-ERR 1DATA 2DATA-ERR 2 +KEV KEV MILLI-EV MILLI-EV + 3424.2 .5 295. 44. + 4093.7 .6 112. 17. + 4144.9 .6 136. 21. + 4625.6 .7 97. 16. + 4901.4 1. 78. 14. + 5164.4 .9 62. 12. + 5219.5 .8 208. 34. + 5381.6 1. 69. 16. + 5421.7 .7 141. 24. + 5432.7 .7 139. 23. + 5523.2 .7 459. 71. + 5551.1 .8 156. 28. + 5586.7 1.2 107. 22. + 5660.6 1.3 150. 28. + 5713.8 1.4 124. 25. + 5733. 1.1 135. 26. + 5824.5 .8 237. 40. + 5862.6 1.3 136. 27. + 5912.2 .7 518. 82. + 5965.1 .9 101. 23. + 5995.8 .8 305. 49. + 6016. .8 315. 51. + 6034.8 .7 510. 79. + 6047. .8 308. 50. + 6149.6 .7 869. 133. + 6171.4 .7 874. 134. + 6223.7 .8 538. 85. + 6322.2 .6 1272. 194. + 6363.8 1.1 891. 139. + 6555.1 1. 233. 44. + 6562.2 .7 427. 72. + 6586.7 1.1 374. 69. + 6596.3 1.1 386. 70. + 6615.3 1.3 261. 53. + 6625.8 1. 476. 82. + 6652.7 1.2 209. 46. + 6678. .9 372. 65. + 6733.4 1. 512. 86. + 6802.4 1. 372. 68. + 6931.8 1.3 283. 59. + 7068.5 .8 1075. 172. + 7113.6 .9 820. 135. +ENDDATA 44 +ENDSUBENT 51 +SUBENT M0821005 20110622 20111003 20110921 M059 +BIB 1 2 +REACTION 1(62-SM-144(G,0),,EN) Excitation energy Ex. + 2(62-SM-144(G,EL),,WID/STR,,MSC) +ENDBIB 2 +NOCOMMON 0 0 +DATA 4 29 +DATA 1DATA-ERR 1DATA 2DATA-ERR 2 +KEV KEV MILLI-EV MILLI-EV + 3225.7 .6 289. 44. + 3817.9 1.1 64. 12. + 3890.4 .6 258. 39. + 3965.3 .8 107. 18. + 4261.2 .7 270. 43. + 4840.2 .8 198. 34. + 5103.5 .9 171. 30. + 5149.6 1. 381. 61. + 5284.9 1. 172. 32. + 5483.1 1.1 258. 46. + 5644.9 .8 470. 76. + 5848.6 .7 1252. 191. + 5911.2 1.1 343. 58. + 5926.1 .7 869. 135. + 5944.9 .6 1566. 240. + 5994.1 .8 634. 104. + 6018.1 .8 227. 47. + 6051.6 1.1 231. 50. + 6068.4 .9 393. 70. + 6112.5 .9 705. 116. + 6172. 1.1 292. 60. + 6245. 1.3 725. 127. + 6259.7 1.3 498. 97. + 6317.2 1. 1191. 189. + 6366.1 .9 425. 80. + 6451.4 .8 657. 114. + 6470.4 1.2 721. 139. + 6484.2 1.7 381. 80. + 6987.6 1.2 691. 143. +ENDDATA 31 +ENDSUBENT 38 +ENDENTRY 5 diff --git a/exforall/O00/O0077.x4 b/exforall/O00/O0077.x4 index 68761cd6e..37ab1e7a9 100644 --- a/exforall/O00/O0077.x4 +++ b/exforall/O00/O0077.x4 @@ -1,139 +1,158 @@ -ENTRY O0077 970121 20050926 0000 -SUBENT O0077001 970121 20050926 0000 -BIB 11 33 -TITLE Formation Cross Sections of Various Radionuclides from - Ni,Fe,Si,Mg,O and C For Protons of Energies Between - 0.5 and 2.9 GeV. -AUTHOR (G.V.S.RAYUDU) -HISTORY (950214C) - (961123A) Correction For All Subenties. - (970121U) Last checking has been done. +ENTRY O0077 20110312 20111003 20110913 O045 +SUBENT O0077001 20110312 20111003 20110913 O045 +BIB 10 27 +TITLE Formation cross sections of various radionuclides + from Ni,Fe,Si,Mg,O and C for protons of energies + between 0.5 and 2.9 GeV. +AUTHOR (G.V.S.Rayudu) INSTITUTE (1USACAR) -REFERENCE (J,JIN,30,2311,68) -MONITOR ((MONIT)13-AL-27(P,N+3P)11-NA-24,CUM/UND,SIG,,,EXP) -DETECTOR (NAICR).The Rest of the Nuclides were Measured Using - A 5*5 Cm Nai(TL) Scintillation Detector in Conjunction - With a 256-Channel Pulse-Height Analyzer. - Co-56 was Measured Using a Low-Beta-Sharp Counter. -MONIT-REF (C0224001,J.B.CUMMING+,J,PR,128,2392,62) - (B0022001,J.B.CUMMING,J,ARN,13,261,63) +REFERENCE (J,JIN,30,2311,1968) +MONITOR ((MONIT)13-AL-27(P,N+3P)11-NA-24,CUM,SIG) +DETECTOR (NAICR).The rest of the nuclides were measured using + a 5*5 cm NaI(Tl) scintillation detector in conjunction + with a 256-channel pulse-height Analyzer. + Co-56 was measured using a low-beta-sharp counter. +MONIT-REF (C0224001,J.B.Cumming+,J,PR,128,2392,1962) + (B0022001,J.B.Cumming,J,ARN,13,261,1963) + An average cross section was chosen. + All cross sections were measured relative to those for + the 27Al(p,3pn)24Na monitor reaction, using 1 ml + aluminium foil. FACILITY (SYNCY,1USABNL).The Cosmotron at the Brookhaven National Laboratory. METHOD (ACTIV,INTB,SITA) -ERR-ANALYS (ERR-1).About 15 Per Cent Overall Uncertainty was - Estimated For Co-56,Mn-54,Mn-52,Cr-51,V-48,Na-24 and - Be-7 Cross Sections from Fe and Ni,at 1.5,2.2 and - 2.9-GeV Proton Energies. - (ERR-2).About 20-25 Per Cent Uncertainty was Estimated - For the Same Nuclides at 0.5 and 0.8 GeV,Because of Low - Beam Currents at these Enegries,Whereas in the Case of - P-32 from Fe and Ni. - (ERR-3).An Average of 12 % Uncertainty was Estimated - At All Energies. - (ERR-4).For the Cross Sections Measurements of Cr-48, - Sc-47, Sc-44-M from Fe;Na-24,Na-22 and be-7 from Si and - Mg, and be-7 from C and O,About 20 Per Cent Uncertainty - Was Estimated at All Energies. -ENDBIB 33 -COMMON 5 3 -ERR-1 ERR-2 ERR-3 ERR-4 MONIT -PER-CENT PER-CENT PER-CENT PER-CENT MB - 15. 25. 12. 20. 10. +HISTORY (19950214C) + (19961123A) Correction for all subentries. + (19970121U) Last checking has been done. + (20110312A) SD: In REACTION code: SF9=EXP deleted + from all Subents. DATA in Subent 012 corrected. + Two digits in year changed on four. + ERR-ANALYS moved to Subents from Subent 001. +ENDBIB 27 +COMMON 1 3 +MONIT +MB + 10. ENDCOMMON 3 -ENDSUBENT 40 -SUBENT O0077002 970121 20050926 0000 -BIB 5 6 -REACTION (26-FE-0(P,X)27-CO-56,IND,SIG,,,EXP) -SAMPLE Metal Foil of Iron,Thickness 40 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 34 +SUBENT O0077002 20110312 20111003 20110913 O045 +BIB 7 10 +REACTION (26-FE-0(P,X)27-CO-56,IND,SIG) +SAMPLE Metal foil of Iron,thickness 40 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. RAD-DET (27-CO-56,B+) DECAY-DATA (27-CO-56,77.D,B+,,0.18) -ENDBIB 6 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 3, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 10 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 0.94 0.8 0.81 - 1.5 0.82 - 2.2 0.67 - 2.9 0.71 + 1.5 0.82 15. + 2.2 0.67 15. + 2.9 0.71 15. ENDDATA 7 -ENDSUBENT 18 -SUBENT O0077003 970121 20050926 0000 -BIB 5 7 -REACTION (26-FE-0(P,X)25-MN-54,,SIG,,,EXP) Independent -SAMPLE Metal Foil of Iron,Thickness 40 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 22 +SUBENT O0077003 20110312 20111003 20110913 O045 +BIB 7 11 +REACTION (26-FE-0(P,X)25-MN-54,,SIG) Independent +SAMPLE Metal foil of Iron,thickness 40 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. (GSPEC) RAD-DET (25-MN-54,DG) DECAY-DATA (25-MN-54,310.D,DG,850.,1.) -ENDBIB 7 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 3, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 11 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 31. 0.8 28. - 1.5 34. - 2.2 28. - 2.9 27. + 1.5 34. 15. + 2.2 28. 15. + 2.9 27. 15. ENDDATA 7 -ENDSUBENT 19 -SUBENT O0077004 970121 20050926 0000 -BIB 6 8 -REACTION (26-FE-0(P,X)25-MN-52-G,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Iron,Thickness 40 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 23 +SUBENT O0077004 20110312 20111003 20110913 O045 +BIB 8 12 +REACTION (26-FE-0(P,X)25-MN-52-G,CUM,SIG) +SAMPLE Metal foil of Iron,thickness 40 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. RAD-DET (25-MN-52-G,B+) DECAY-DATA (25-MN-52-G,5.7D,B+,,0.33) -COMMENT - By Compiler - Any Information About B+ Detector is - Absent. -ENDBIB 8 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +COMMENT - By Compiler - Any information about B+ detector is + absent. +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 3, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 12 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 14.7 0.8 14.1 - 1.5 10.3 - 2.2 10.4 - 2.9 10.1 + 1.5 10.3 15. + 2.2 10.4 15. + 2.9 10.1 15. ENDDATA 7 -ENDSUBENT 20 -SUBENT O0077005 970121 20050926 0000 -BIB 5 7 -REACTION (26-FE-0(P,X)24-CR-51,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Iron,Thickness 40 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 24 +SUBENT O0077005 20110312 20111003 20110913 O045 +BIB 7 11 +REACTION (26-FE-0(P,X)24-CR-51,CUM,SIG) +SAMPLE Metal foil of Iron,thickness 40 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. (GSPEC) RAD-DET (24-CR-51,DG) DECAY-DATA (24-CR-51,27.8D,DG,320.,0.10) -ENDBIB 7 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 3, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 11 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 21.4 0.8 20.1 - 1.5 17.3 - 2.2 14.6 - 2.9 15.8 + 1.5 17.3 15. + 2.2 14.6 15. + 2.9 15.8 15. ENDDATA 7 -ENDSUBENT 19 -SUBENT O0077006 970121 20050926 0000 -BIB 5 5 -REACTION (26-FE-0(P,X)24-CR-48,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Iron,Thickness 40 Mg/Cm**2,was Used. +ENDSUBENT 23 +SUBENT O0077006 20110312 20111003 20110913 O045 +BIB 7 10 +REACTION (26-FE-0(P,X)24-CR-48,CUM,SIG) +SAMPLE Metal foil of Iron, thickness 40 mg/cm**2,was used. METHOD (GSPEC) RAD-DET (24-CR-48,DG) DECAY-DATA (24-CR-48,23.HR,DG,120.,0.95) -ENDBIB 5 -NOCOMMON +ERR-ANALYS (DATA-ERR).For the Cross Sections Measurements of Cr-48 + Sc-47, Sc-44-M from Fe;Na-24,Na-22 and Be-7 from Si and + Mg, and Be-7 from C and O,about 20% uncertainty + was estimated at all energies. +STATUS (TABLE) Table 3, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 10 +COMMON 1 3 +DATA-ERR +PER-CENT + 20. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -143,37 +162,47 @@ GEV MB 2.2 0.38 2.9 0.41 ENDDATA 7 -ENDSUBENT 17 -SUBENT O0077007 970121 20050926 0000 -BIB 5 7 -REACTION (26-FE-0(P,X)23-V-48,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Iron,Thickness 40 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 26 +SUBENT O0077007 20110312 20111003 20110913 O045 +BIB 7 11 +REACTION (26-FE-0(P,X)23-V-48,CUM,SIG) +SAMPLE Metal foil of Iron, thickness 40 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. (GSPEC) RAD-DET (23-V-48,DG) DECAY-DATA (23-V-48,16.1D,DG,1330.,1.) -ENDBIB 7 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 3, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 11 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 10.7 0.8 6.8 - 1.5 6.3 - 2.2 6.3 - 2.9 4.9 + 1.5 6.3 15. + 2.2 6.3 15. + 2.9 4.9 15. ENDDATA 7 -ENDSUBENT 19 -SUBENT O0077008 970121 20050926 0000 -BIB 5 5 -REACTION (26-FE-0(P,X)21-SC-47,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Iron,Thickness 40 Mg/Cm**2,was Used. +ENDSUBENT 23 +SUBENT O0077008 20110312 20111003 20110913 O045 +BIB 7 7 +REACTION (26-FE-0(P,X)21-SC-47,CUM,SIG) +SAMPLE Metal foil of Iron, thickness 40 mg/cm**2,was used. METHOD (GSPEC) RAD-DET (21-SC-47,DG) DECAY-DATA (21-SC-47,3.4D,DG,160.,0.70) -ENDBIB 5 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 20% overall uncertainty was estimated +STATUS (TABLE) Table 3, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 7 +COMMON 1 3 +DATA-ERR +PER-CENT + 20. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -183,16 +212,22 @@ GEV MB 2.2 1.29 2.9 1.27 ENDDATA 7 -ENDSUBENT 17 -SUBENT O0077009 970121 20050926 0000 -BIB 5 5 -REACTION (26-FE-0(P,X)21-SC-44-M,IND,SIG,,,EXP) -SAMPLE Metal Foil of Iron,Thickness 40 Mg/Cm**2,was Used. +ENDSUBENT 23 +SUBENT O0077009 20110312 20111003 20110913 O045 +BIB 7 7 +REACTION (26-FE-0(P,X)21-SC-44-M,IND,SIG) +SAMPLE Metal foil of Iron, thickness 40 mg/cm**2,was used. RAD-DET (21-SC-44-M,DG) DECAY-DATA (21-SC-44-M,2.4D,DG,270.,0.88) METHOD (GSPEC) -ENDBIB 5 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 20% overall uncertainty was estimated +STATUS (TABLE) Table 3, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 7 +COMMON 1 3 +DATA-ERR +PER-CENT + 20. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -202,18 +237,25 @@ GEV MB 2.2 4.2 2.9 4.0 ENDDATA 7 -ENDSUBENT 17 -SUBENT O0077010 970121 20050926 0000 -BIB 6 7 -REACTION (26-FE-0(P,X)15-P-32,IND,SIG,,,EXP) -SAMPLE Metal Foil of Iron,Thickness 40 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 23 +SUBENT O0077010 20110312 20111003 20110913 O045 +BIB 9 10 +REACTION (26-FE-0(P,X)15-P-32,IND,SIG) +SAMPLE Metal foil of Iron, thickness 40 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. RAD-DET (15-P-32,B-) DECAY-DATA (15-P-32,14.3D,B-,,1.) COMMENT -By Compiler- Author did not Describe Detector For B-. -ENDBIB 7 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 12% uncertainty was estimated +STATUS (TABLE) Table 3, J.Inorg.Nucl.Chem.30(1968)2311 +HISTORY (20110312A) SD:last value for DATA corrected (6.2->6.1) +ENDBIB 10 +COMMON 1 3 +DATA-ERR +PER-CENT + 12. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -221,168 +263,203 @@ GEV MB 0.8 3.6 1.5 5.4 2.2 6.1 - 2.9 6.2 + 2.9 6.1 ENDDATA 7 -ENDSUBENT 19 -SUBENT O0077011 970121 20050926 0000 -BIB 5 5 -REACTION (26-FE-0(P,X)11-NA-24,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Iron,Thickness 40 Mg/Cm**2,was Used. +ENDSUBENT 26 +SUBENT O0077011 20110312 20111003 20110913 O045 +BIB 7 9 +REACTION (26-FE-0(P,X)11-NA-24,CUM,SIG) +SAMPLE Metal foil of Iron, thickness 40 mg/cm**2,was used. METHOD (GSPEC) RAD-DET (11-NA-24,DG) DECAY-DATA (11-NA-24,15.HR,DG,2750.,1.) -ENDBIB 5 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 3, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 9 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 0.29 0.8 1.07 - 1.5 3.2 - 2.2 3.8 - 2.9 3.9 + 1.5 3.2 15. + 2.2 3.8 15. + 2.9 3.9 15. ENDDATA 7 -ENDSUBENT 17 -SUBENT O0077012 970121 20050926 0000 -BIB 5 7 -REACTION (26-FE-0(P,X)4-BE-7,,SIG,,,EXP) Independent -SAMPLE Metal Foil of Iron,Thickness 40 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 21 +SUBENT O0077012 20110312 20111003 20110913 O045 +BIB 8 12 +REACTION (26-FE-0(P,X)4-BE-7,,SIG) Independent +SAMPLE Metal foil of Iron, thickness 40 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. (GSPEC) RAD-DET (4-BE-7,DG) DECAY-DATA (4-BE-7,53.D,DG,470.,0.11) -ENDBIB 7 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB - 0.5 0.94 - 0.8 0.81 - 1.5 0.82 - 2.2 0.67 - 2.9 0.71 +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 3, J.Inorg.Nucl.Chem.30(1968)2311 +HISTORY (20110312A) SD: values in col.DATA corrected. +ENDBIB 12 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT + 0.5 1.21 + 0.8 2.1 + 1.5 3.2 15. + 2.2 5.7 15. + 2.9 4.7 15. ENDDATA 7 -ENDSUBENT 19 -SUBENT O0077013 970121 20050926 0000 -BIB 6 9 -REACTION (28-NI-0(P,X)27-CO-56,IND,SIG,,,EXP) -SAMPLE Metal Foil of Nickel,Thickness 45 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 24 +SUBENT O0077013 20110312 20111003 20110913 O045 +BIB 8 13 +REACTION (28-NI-0(P,X)27-CO-56,IND,SIG) +SAMPLE Metal foil of Nickel, thickness 45 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. RAD-DET (27-CO-56,B+) DECAY-DATA (27-CO-56,77.D,B+,,0.18) -CRITIQUE Author Suggestes That Independent Cross Section was - Measured. But any Information About Cross Section For - Parent of Co-56 is Absent. -ENDBIB 9 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +CRITIQUE Author suggests that independent cross section was + measured. But any information about cross section For + parent of Co-56 is absent. +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 4, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 13 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 32. 0.8 25. - 1.5 25. - 2.2 28. - 2.9 21. + 1.5 25. 15. + 2.2 28. 15. + 2.9 21. 15. ENDDATA 7 -ENDSUBENT 21 -SUBENT O0077014 970121 20050926 0000 -BIB 5 7 -REACTION (28-NI-0(P,X)25-MN-54,,SIG,,,EXP) Independent -SAMPLE Metal Foil of Nickel,Thickness 45 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 25 +SUBENT O0077014 20110312 20111003 20110913 O045 +BIB 7 11 +REACTION (28-NI-0(P,X)25-MN-54,,SIG) Independent +SAMPLE Metal foil of Nickel, thickness 45 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. (GSPEC) RAD-DET (25-MN-54,DG) DECAY-DATA (25-MN-54,310.D,DG,850.,1.) -ENDBIB 7 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 4, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 11 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 6.6 0.8 4.5 - 1.5 4.9 - 2.2 4.9 - 2.9 4.2 + 1.5 4.9 15. + 2.2 4.9 15. + 2.9 4.2 15. ENDDATA 7 -ENDSUBENT 19 -SUBENT O0077015 970121 20050926 0000 -BIB 6 8 -REACTION (28-NI-0(P,X)25-MN-52-G,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Nickel,Thickness 45 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 23 +SUBENT O0077015 20110312 20111003 20110913 O045 +BIB 8 12 +REACTION (28-NI-0(P,X)25-MN-52-G,CUM,SIG) +SAMPLE Metal foil of Nickel, thickness 45 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. RAD-DET (25-MN-52-G,B+) DECAY-DATA (25-MN-52-G,5.7D,B+,,0.33) -COMMENT -By Compiler- Any Information For Detector of B+ is - Absent. -ENDBIB 8 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +COMMENT -By Compiler- Any information for detector of B+ is + absent. +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 4, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 12 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 18.7 0.8 12.0 - 1.5 12.4 - 2.2 12.2 - 2.9 8.9 + 1.5 12.4 15. + 2.2 12.2 15. + 2.9 8.9 15. ENDDATA 7 -ENDSUBENT 20 -SUBENT O0077016 970121 20050926 0000 -BIB 5 7 -REACTION (28-NI-0(P,X)24-CR-51,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Nickel,Thickness 45 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 24 +SUBENT O0077016 20110312 20111003 20110913 O045 +BIB 7 11 +REACTION (28-NI-0(P,X)24-CR-51,CUM,SIG) +SAMPLE Metal foil of Nickel,thickness 45 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. (GSPEC) RAD-DET (24-CR-51,DG) DECAY-DATA (24-CR-51,27.8D,DG,320.0,0.10) -ENDBIB 7 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 4, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 11 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 18.2 0.8 15.8 - 1.5 14.1 - 2.2 14.7 - 2.9 11.6 + 1.5 14.1 15. + 2.2 14.7 15. + 2.9 11.6 15. ENDDATA 7 -ENDSUBENT 19 -SUBENT O0077017 970121 20050926 0000 -BIB 5 7 -REACTION (28-NI-0(P,X)23-V-48,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Nickel,Thickness 45 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 23 +SUBENT O0077017 20110312 20111003 20110913 O045 +BIB 7 11 +REACTION (28-NI-0(P,X)23-V-48,CUM,SIG) +SAMPLE Metal foil of Nickel,thickness 45 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. (GSPEC) RAD-DET (23-V-48,DG) DECAY-DATA (23-V-48,16.1D,DG,1330.,1.) -ENDBIB 7 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 4, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 11 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 6.1 0.8 7.1 - 1.5 7.9 - 2.2 8.8 - 2.9 8.5 + 1.5 7.9 15. + 2.2 8.8 15. + 2.9 8.5 15. ENDDATA 7 -ENDSUBENT 19 -SUBENT O0077018 970121 20050926 0000 -BIB 6 7 -REACTION (28-NI-0(P,X)15-P-32,IND,SIG,,,EXP) -SAMPLE Metal Foil of Nickel,Thickness 45 Mg/Cm**2,was Used. +ENDSUBENT 23 +SUBENT O0077018 20110312 20111003 20110913 O045 +BIB 8 9 +REACTION (28-NI-0(P,X)15-P-32,IND,SIG) +SAMPLE Metal foil of Nickel,thickness 45 mg/cm**2,was used. METHOD (CHSEP) RAD-DET (15-P-32,B-) DECAY-DATA (15-P-32,14.3D,B-,,1.) COMMENT -By Compiler- Any Information For Detector of B- Is Absent. -ENDBIB 7 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 12% uncertainty was estimated +STATUS (TABLE) Table 4, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 9 +COMMON 1 3 +DATA-ERR +PER-CENT + 12. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -392,56 +469,70 @@ GEV MB 2.2 4.5 2.9 4.6 ENDDATA 7 -ENDSUBENT 19 -SUBENT O0077019 970121 20050926 0000 -BIB 5 5 -REACTION (28-NI-0(P,X)11-NA-24,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Nickel,Thickness 45 Mg/Cm**2,was Used. +ENDSUBENT 25 +SUBENT O0077019 20110312 20111003 20110913 O045 +BIB 7 9 +REACTION (28-NI-0(P,X)11-NA-24,CUM,SIG) +SAMPLE Metal foil of Nickel,thickness 45 mg/cm**2,was used. METHOD (GSPEC) RAD-DET (11-NA-24,DG) DECAY-DATA (11-NA-24,15.HR,DG,2750.,1.) -ENDBIB 5 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 4, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 9 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 0.185 0.8 0.65 - 1.5 1.82 - 2.2 3.4 - 2.9 3.9 + 1.5 1.82 15. + 2.2 3.4 15. + 2.9 3.9 15. ENDDATA 7 -ENDSUBENT 17 -SUBENT O0077020 970121 20050926 0000 -BIB 5 7 -REACTION (28-NI-0(P,X)4-BE-7,,SIG,,,EXP) Independent -SAMPLE Metal Foil of Nickel,Thickness 45 Mg/Cm**2,was Used. -METHOD (CHSEP) Chemical Separations were Started Three Days - After the Irradiations. +ENDSUBENT 21 +SUBENT O0077020 20110312 20111003 20110913 O045 +BIB 7 11 +REACTION (28-NI-0(P,X)4-BE-7,,SIG) Independent +SAMPLE Metal foil of Nickel,thickness 45 mg/cm**2,was used. +METHOD (CHSEP) Chemical separations were started three days + after the irradiations. (GSPEC) RAD-DET (4-BE-7,DG) DECAY-DATA (4-BE-7,53.D,DG,470.,0.11) -ENDBIB 7 -NOCOMMON -DATA 2 5 -EN DATA -GEV MB +ERR-ANALYS (DATA-ERR).About 15% overall uncertainty was estimated + .About 20-25% uncertainty was estimated at 0.5 and + 0.8 GeV,because of low beam currents at these energies. +STATUS (TABLE) Table 4, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 11 +NOCOMMON 0 0 +DATA 3 5 +EN DATA DATA-ERR +GEV MB PER-CENT 0.5 1.62 0.8 2.4 - 1.5 4.9 - 2.2 6.5 - 2.9 7.2 + 1.5 4.9 15. + 2.2 6.5 15. + 2.9 7.2 15. ENDDATA 7 -ENDSUBENT 19 -SUBENT O0077021 970121 20050926 0000 -BIB 5 5 -REACTION (14-SI-0(P,X)11-NA-24,CUM,SIG,,,EXP) -SAMPLE Thin Slice of Silicon,Thickness 125 Mg/Cm**2,was Used. +ENDSUBENT 23 +SUBENT O0077021 20110312 20111003 20110913 O045 +BIB 7 7 +REACTION (14-SI-0(P,X)11-NA-24,CUM,SIG) +SAMPLE Thin Slice of Silicon,thickness 125 mg/cm**2,was used. RAD-DET (11-NA-24,DG) DECAY-DATA (11-NA-24,15.HR,DG,2750.,1.) METHOD (GSPEC) -ENDBIB 5 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 20% overall uncertainty was estimated +STATUS (TABLE) Table 5, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 7 +COMMON 1 3 +DATA-ERR +PER-CENT + 20. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -451,16 +542,22 @@ GEV MB 2.2 4.0 2.9 5.2 ENDDATA 7 -ENDSUBENT 17 -SUBENT O0077022 970121 20050926 0000 -BIB 5 5 -REACTION (14-SI-0(P,X)11-NA-22,CUM,SIG,,,EXP) -SAMPLE Thin Slice of Silicon,Thickness 125 Mg/Cm**2,was Used. +ENDSUBENT 23 +SUBENT O0077022 20110312 20111003 20110913 O045 +BIB 7 7 +REACTION (14-SI-0(P,X)11-NA-22,CUM,SIG) +SAMPLE Thin Slice of Silicon,thickness 125 mg/cm**2,was used. RAD-DET (11-NA-22,DG) DECAY-DATA (11-NA-22,2.58YR,DG,1280.,1.) METHOD (GSPEC) -ENDBIB 5 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 20% overall uncertainty was estimated +STATUS (TABLE) Table 5, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 7 +COMMON 1 3 +DATA-ERR +PER-CENT + 20. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -470,16 +567,22 @@ GEV MB 2.2 8.4 2.9 9.1 ENDDATA 7 -ENDSUBENT 17 -SUBENT O0077023 970121 20050926 0000 -BIB 5 5 -REACTION (14-SI-0(P,X)4-BE-7,,SIG,,,EXP) Independent -SAMPLE Thin Slice of Silicon,Thickness 125 Mg/Cm**2,was Used. +ENDSUBENT 23 +SUBENT O0077023 20110312 20111003 20110913 O045 +BIB 7 7 +REACTION (14-SI-0(P,X)4-BE-7,,SIG) Independent +SAMPLE Thin Slice of Silicon,thickness 125 mg/cm**2,was used. RAD-DET (4-BE-7,DG) DECAY-DATA (4-BE-7,53.D,DG,470.,0.11) METHOD (GSPEC) -ENDBIB 5 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 20% overall uncertainty was estimated +STATUS (TABLE) Table 5, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 7 +COMMON 1 3 +DATA-ERR +PER-CENT + 20. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -489,16 +592,22 @@ GEV MB 2.2 3.0 2.9 4.1 ENDDATA 7 -ENDSUBENT 17 -SUBENT O0077024 970121 20050926 0000 -BIB 5 5 -REACTION (12-MG-0(P,X)11-NA-24,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Magnesium,Thickness 22 Mg/Cm**2,was Used. +ENDSUBENT 23 +SUBENT O0077024 20110312 20111003 20110913 O045 +BIB 7 7 +REACTION (12-MG-0(P,X)11-NA-24,CUM,SIG) +SAMPLE Metal foil of Magnesium,thickness 22 mg/cm**2,was used. RAD-DET (11-NA-24,DG) DECAY-DATA (11-NA-24,15.HR,DG,2750.,1.) METHOD (GSPEC) -ENDBIB 5 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 20% overall uncertainty was estimated +STATUS (TABLE) Table 5, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 7 +COMMON 1 3 +DATA-ERR +PER-CENT + 20. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -508,16 +617,22 @@ GEV MB 2.2 6.8 2.9 6.9 ENDDATA 7 -ENDSUBENT 17 -SUBENT O0077025 970121 20050926 0000 -BIB 5 5 -REACTION (12-MG-0(P,X)11-NA-22,CUM,SIG,,,EXP) -SAMPLE Metal Foil of Magnesium,Thickness 22 Mg/Cm**2,was Used. +ENDSUBENT 23 +SUBENT O0077025 20110312 20111003 20110913 O045 +BIB 7 7 +REACTION (12-MG-0(P,X)11-NA-22,CUM,SIG) +SAMPLE Metal foil of Magnesium,thickness 22 mg/cm**2,was used. RAD-DET (11-NA-22,DG) DECAY-DATA (11-NA-22,2.58YR,DG,1280.,1.) METHOD (GSPEC) -ENDBIB 5 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 20% overall uncertainty was estimated +STATUS (TABLE) Table 5, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 7 +COMMON 1 3 +DATA-ERR +PER-CENT + 20. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -527,16 +642,22 @@ GEV MB 2.2 15.3 2.9 15.4 ENDDATA 7 -ENDSUBENT 17 -SUBENT O0077026 970121 20050926 0000 -BIB 5 5 -REACTION (12-MG-0(P,X)4-BE-7,,SIG,,,EXP) Independent -SAMPLE Metal Foil of Magnesium,Thickness 22 Mg/Cm**2,was Used. +ENDSUBENT 23 +SUBENT O0077026 20110312 20111003 20110913 O045 +BIB 7 7 +REACTION (12-MG-0(P,X)4-BE-7,,SIG) Independent +SAMPLE Metal foil of Magnesium,thickness 22 mg/cm**2,was used. RAD-DET (4-BE-7,DG) DECAY-DATA (4-BE-7,53.D,DG,470.,0.11) METHOD (GSPEC) -ENDBIB 5 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 20% overall uncertainty was estimated +STATUS (TABLE) Table 5, J.Inorg.Nucl.Chem.30(1968)2311 +ENDBIB 7 +COMMON 1 3 +DATA-ERR +PER-CENT + 20. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -546,17 +667,24 @@ GEV MB 2.2 10.8 2.9 12.1 ENDDATA 7 -ENDSUBENT 17 -SUBENT O0077027 970121 20050926 0000 -BIB 5 6 -REACTION (6-C-12(P,3D)4-BE-7,UND,SIG,,,EXP) Independent -SAMPLE Polyethylene (85 PER CENT C),Thickness 75 Mg/Cm**2,. - Was Used. +ENDSUBENT 23 +SUBENT O0077027 20110312 20111003 20110913 O045 +BIB 8 9 +REACTION (6-C-12(P,X)4-BE-7,,SIG) Independent +SAMPLE Polyethylene (85% C),thickness 75 mg/cm**2 + was used. RAD-DET (4-BE-7,DG) DECAY-DATA (4-BE-7,53.D,DG,470.,0.11) METHOD (GSPEC) -ENDBIB 6 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 20% overall uncertainty was estimated +STATUS (TABLE) Table 5, J.Inorg.Nucl.Chem.30(1968)2311 +HISTORY (20110312A) SD: SF3 changed in REACTION code (3D->X) +ENDBIB 9 +COMMON 1 3 +DATA-ERR +PER-CENT + 20. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -566,16 +694,24 @@ GEV MB 2.2 10.8 2.9 10.1 ENDDATA 7 -ENDSUBENT 18 -SUBENT O0077028 970121 20050926 0000 -BIB 5 5 -REACTION (8-O-16(P,5N+5P)4-BE-7,UND,SIG,,,EXP) Independent -SAMPLE Delrin (40P%-C,53%-O),Thickness 75 Mg/Cm**2,was Used. +ENDSUBENT 25 +SUBENT O0077028 20110312 20111003 20110913 O045 +BIB 8 9 +REACTION (8-O-16(P,X)4-BE-7,,SIG) Independent +SAMPLE Delrin (40P%-C,53%-O), thickness 75 mg/cm**2,was used. RAD-DET (4-BE-7,DG) DECAY-DATA (4-BE-7,53.D,DG,470.,0.11) METHOD (GSPEC) -ENDBIB 5 -NOCOMMON +ERR-ANALYS (DATA-ERR).About 20% overall uncertainty was estimated +STATUS (TABLE) Table 5, J.Inorg.Nucl.Chem.30(1968)2311 +HISTORY (20110312A) SD: SF3 changed in REACTION code + SF3=5n+5p => X +ENDBIB 9 +COMMON 1 3 +DATA-ERR +PER-CENT + 20. +ENDCOMMON 3 DATA 2 5 EN DATA GEV MB @@ -585,5 +721,5 @@ GEV MB 2.2 10.9 2.9 10.2 ENDDATA 7 -ENDSUBENT 17 +ENDSUBENT 25 ENDENTRY 28 diff --git a/exforall/O01/O0187.x4 b/exforall/O01/O0187.x4 index 46b8290b8..431aefc70 100644 --- a/exforall/O01/O0187.x4 +++ b/exforall/O01/O0187.x4 @@ -1,231 +1,236 @@ -ENTRY O0187 970113 20050926 0000 -SUBENT O0187001 970113 20050926 0000 -BIB 13 29 +ENTRY O0187 20110312 20111003 20110913 O045 +SUBENT O0187001 20110312 20111003 20110913 O045 +BIB 13 44 TITLE High Spin States in Pb-208. -AUTHOR (D.COOK,N.M.HINTZ,M.M.GAZZALY,G.PAULETTA,R.W.FERGERSON, - G.W.HOFFMANN,J.B.MCCLELLAND,K.W.JONES) +AUTHOR (D.Cook,N.M.Hintz,M.M.Gazzaly,G.Pauletta, + R.W.Fergerson, G.W.Hoffmann,J.B.McClelland,K.W.Jones) INSTITUTE (1USAMIN) (1USATEX) (1USALAS) -REFERENCE (J,PR/C,35,456,87) -HISTORY (960304C) - (960802) Data are Recalculated to Wave Number. - (970113U) Last checking has been done. -SAMPLE An Isotopically Enriched (98.69%),Rolled,Self- - Supporting Foil of Pb-208 was Used.The Effective Area - Density of this Nonuniform Target,21.4Mg/Cm**2,was - Determined by Comparing Measured Cross Sections to - Those Obtained from Two Other Pb-208 Targets of Known - Area Density. -ADD-RES (COMP).The Distorted Wave Impulse Approximation. +REFERENCE (J,PR/C,35,456,1987) +SAMPLE An isotopically enriched (98.69%),rolled,self- + supporting foil of Pb-208 was used. The effective area + density of this nonuniform target,21.4mg/cm**2,was + determined by comparing measured cross sections to + those obtained from two other Pb-208 targets of known + area density. +ADD-RES (COMP).The distorted wave impulse approximation. (POT) DETECTOR (MAGSP) - (IOCH).The Relative Beam Intensity was Monitored by - Two Ionization Chambers in the Rear of the Scattering - Chamber. + (IOCH).The relative beam intensity was monitored by + two ionization chambers in the rear of the scattering + chamber. FACILITY (MESON,1USALAS) +MONITOR The absolute cross sections were obtained by + normalizing to p-p cross sections calculated by the + program SAID (R.Arndt,computer program SAID - + unpublished) + The p-p cross section was measured at 11. and 16. degr. + Absolute normalization factors obtained at the two + angles are consistent to 4%. An independent measurement + of the 208Pb cross section at 334 MeV by Bertrand (Phys + Rev.34,45,1986 + private comm.) agrees to within 5%. METHOD (SITA,BCINT) -COMMENT /by Compiler/.The Authors Data (1/FM) Were - Recalculated by Compiler in MeV/C Using Formulae- - P=197.37*Q(1/FM). -ERR-ANALYS (ERR-S).Data-Point Reader Uncertainty For Wave Number. +ERR-ANALYS (MONIT-ERR) Overall uncertainty in normalization + (See MONITOR) + (ERR-DIG).Data-Point Reader Uncertainty. STATUS (CURVE).By CAJAD. -ENDBIB 29 -COMMON 2 3 -EN ANG -MEV ADEG - 318. 28. +HISTORY (19960304C) + (19960802A) Data are recalculated to wave number. + (19970113U) Last checking has been done. + (20110312A) SD: In Subents 002 - 006 col. MISC changed + on MOM-TR and col. q - deleted => Comment from + compiler about q calculation deleted. + In REACTION code: SF9=EXP deleted from all + Subents. DATA in Subent 012 corrected. + Two digits in year changed on four. + ANG deleted from COMMON section of Subent 001 +ENDBIB 44 +COMMON 4 3 +EN MONIT-ERR ERR-DIG EN-ERR +MEV PER-CENT PER-CENT MEV + 318. 10. 5. 0.007 ENDCOMMON 3 -ENDSUBENT 36 -SUBENT O0187002 970113 20050926 0000 -BIB 4 4 -REACTION (82-PB-208(P,EL)82-PB-208,,DA,,,EXP) See Fig.3 -MISC-COL (MISC) Linear Momentum Transferred to 208-Pb. -MOM-SEC (MOM-TR,82-PB-208) -ERR-ANALYS (DATA-ERR).Data-Point Reader Uncertainty. -ENDBIB 4 -COMMON 2 3 -ERR-S DATA-ERR -1/FM PER-CENT - 0.011 5. -ENDCOMMON 3 -DATA 3 56 -MOM-TR DATA MISC -1/FM MB/SR MEV/C - 0.50160 6070.0 99.0 - 0.50666 1920.0 100.0 - 0.56645 740.0 111.8 - 0.59077 650.0 116.6 - 0.66879 1030.0 132.0 - 0.66930 940.0 132.1 - 0.67031 750.0 132.3 - 0.74885 1040.0 147.8 - 0.82991 760.0 163.8 - 0.83143 551.0 164.1 - 0.91351 293.0 180.3 - 0.91503 213.0 180.6 - 0.96773 72.0 191.0 - 1.00573 16.7 198.5 - 1.05487 12.2 208.2 - 1.08426 23.1 214.0 - 1.12834 60.4 222.7 - 1.12884 53.1 222.8 - 1.15924 73.0 228.8 - 1.23930 74.0 244.6 - 1.23980 60.9 244.7 - 1.32036 53.9 260.6 - 1.32239 32.4 261.0 - 1.37103 28.6 270.6 - 1.40650 12.5 277.6 - 1.48959 5.67 294.0 - 1.49111 4.12 294.3 - 1.53975 3.53 303.9 - 1.56863 6.7 309.6 - 1.57015 4.86 309.9 - 1.61524 9.2 318.8 - 1.64716 9.3 325.1 - 1.72772 8.2 341.0 - 1.80879 6.19 357.0 - 1.80980 4.95 357.2 - 1.85895 3.61 366.9 - 1.89492 1.39 374.0 - 1.95369 0.74 385.6 - 2.02513 0.74 399.7 - 2.05604 1.02 405.8 - 2.13457 1.42 421.3 - 2.13508 1.25 421.4 - 2.21564 1.04 437.3 - 2.29670 0.76 453.3 - 2.29873 0.48500 453.7 - 2.34737 0.40200 463.3 - 2.38233 0.18700 470.2 - 2.43249 0.11300 480.1 - 2.50342 0.13800 494.1 - 2.54142 0.21600 501.6 - 2.66961 0.21800 526.9 - 2.70254 0.15900 533.4 - 2.75270 0.10200 543.3 - 2.78512 0.08400 549.7 - 2.78816 0.04460 550.3 - 2.83883 0.02360 560.3 +ENDSUBENT 51 +SUBENT O0187002 20110312 20111003 20110913 O045 +BIB 2 3 +REACTION (82-PB-208(P,EL)82-PB-208,,DA) See Fig.3 +HISTORY (20110312A) SD: Col. MISC changed on MOM-TR and + col. q - deleted. +ENDBIB 3 +NOCOMMON 0 0 +DATA 2 56 +MOM-TR DATA +MEV/C MB/SR + 99.0 6070.0 + 100.0 1920.0 + 111.8 740.0 + 116.6 650.0 + 132.0 1030.0 + 132.1 940.0 + 132.3 750.0 + 147.8 1040.0 + 163.8 760.0 + 164.1 551.0 + 180.3 293.0 + 180.6 213.0 + 191.0 72.0 + 198.5 16.7 + 208.2 12.2 + 214.0 23.1 + 222.7 60.4 + 222.8 53.1 + 228.8 73.0 + 244.6 74.0 + 244.7 60.9 + 260.6 53.9 + 261.0 32.4 + 270.6 28.6 + 277.6 12.5 + 294.0 5.67 + 294.3 4.12 + 303.9 3.53 + 309.6 6.7 + 309.9 4.86 + 318.8 9.2 + 325.1 9.3 + 341.0 8.2 + 357.0 6.19 + 357.2 4.95 + 366.9 3.61 + 374.0 1.39 + 385.6 0.74 + 399.7 0.74 + 405.8 1.02 + 421.3 1.42 + 421.4 1.25 + 437.3 1.04 + 453.3 0.76 + 453.7 0.48500 + 463.3 0.40200 + 470.2 0.18700 + 480.1 0.11300 + 494.1 0.13800 + 501.6 0.21600 + 526.9 0.21800 + 533.4 0.15900 + 543.3 0.10200 + 549.7 0.08400 + 550.3 0.04460 + 560.3 0.02360 ENDDATA 58 -ENDSUBENT 71 -SUBENT O0187003 970113 20050926 0000 -BIB 6 6 -REACTION (82-PB-208(P,INL)82-PB-208,PAR,DA,,,EXP) See Fig. 7 +ENDSUBENT 66 +SUBENT O0187003 20110312 20111003 20110913 O045 +BIB 4 5 +REACTION (82-PB-208(P,INL)82-PB-208,PAR,DA) See Fig. 7 EN-SEC (E-LVL,82-PB-208) LEVEL-PROP (82-PB-208,E-LVL=6.74,SPIN=14.,PARITY=-1.) -MISC-COL (MISC) Linear Momentum Transferred to 208-Pb. -MOM-SEC (MOM-TR,82-PB-208) -ERR-ANALYS (DATA-ERR).Data-Point Reader Uncertainty. -ENDBIB 6 -COMMON 3 3 -ERR-S E-LVL DATA-ERR -1/FM MEV PER-CENT - 0.0075 6.74 2.3 +HISTORY (20110312A) SD: Col. MISC changed on MOM-TR and + col. q - deleted. +ENDBIB 5 +COMMON 1 3 +E-LVL +MEV + 6.74 ENDCOMMON 3 -DATA 3 9 -MOM-TR DATA MISC -1/FM MB/SR MEV/C - 1.81487 0.03620 358.2 - 1.92380 0.05080 379.7 - 2.03222 0.07130 401.1 - 2.14116 0.07130 422.6 - 2.24958 0.06660 444.0 - 2.35851 0.06020 465.5 - 2.46694 0.04290 486.9 - 2.68481 0.01310 529.9 - 2.79323 0.00789 551.3 +DATA 2 9 +MOM-TR DATA +MEV/C MB/SR + 358.2 0.03620 + 379.7 0.05080 + 401.1 0.07130 + 422.6 0.07130 + 444.0 0.06660 + 465.5 0.06020 + 486.9 0.04290 + 529.9 0.01310 + 551.3 0.00789 ENDDATA 11 -ENDSUBENT 26 -SUBENT O0187004 970113 20050926 0000 -BIB 6 6 -REACTION (82-PB-208(P,INL)82-PB-208,PAR,DA,,,EXP) See Fig.8 +ENDSUBENT 25 +SUBENT O0187004 20110312 20111003 20110913 O045 +BIB 4 5 +REACTION (82-PB-208(P,INL)82-PB-208,PAR,DA) See Fig.8 EN-SEC (E-LVL,82-PB-208) LEVEL-PROP (82-PB-208,E-LVL=6.10,SPIN=12.,PARITY=+1.) -MISC-COL (MISC) Linear Momentum Transferred to 208-Pb. -MOM-SEC (MOM-TR,82-PB-208) -ERR-ANALYS (DATA-ERR).Data-Point Reader Uncertainty. -ENDBIB 6 -COMMON 3 3 -ERR-S E-LVL DATA-ERR -1/FM MEV PER-CENT - 0.035 6.10 12. +HISTORY (20110312A) SD: Col. MISC changed on MOM-TR and + col. q - deleted. +ENDBIB 5 +COMMON 1 3 +E-LVL +MEV + 6.10 ENDCOMMON 3 -DATA 3 10 -MOM-TR DATA MISC -1/FM MB/SR MEV/C - 1.72265 0.05900 340.0 - 1.82905 0.06500 361.0 - 1.93545 0.06500 382.0 - 2.04185 0.07900 403.0 - 2.14825 0.07400 424.0 - 2.25972 0.05600 446.0 - 2.36611 0.04200 467.0 - 2.47758 0.03300 489.0 - 2.69545 0.01390 532.0 - 2.75118 0.01090 543.0 +DATA 2 10 +MOM-TR DATA +MEV/C MB/SR + 340.0 0.05900 + 361.0 0.06500 + 382.0 0.06500 + 403.0 0.07900 + 424.0 0.07400 + 446.0 0.05600 + 467.0 0.04200 + 489.0 0.03300 + 532.0 0.01390 + 543.0 0.01090 ENDDATA 12 -ENDSUBENT 27 -SUBENT O0187005 970113 20050926 0000 -BIB 6 7 -REACTION (82-PB-208(P,INL)82-PB-208,PAR,DA,,,EXP) See Fig.12 +ENDSUBENT 26 +SUBENT O0187005 20110312 20111003 20110913 O045 +BIB 4 5 +REACTION (82-PB-208(P,INL)82-PB-208,PAR,DA) See Fig.12 EN-SEC (E-LVL,82-PB-208) LEVEL-PROP (82-PB-208,E-LVL=6.43,SPIN=12.,PARITY=-1.) -MISC-COL (MISC) Linear Momentum Transferred to 208-Pb. -MOM-SEC (MOM-TR,82-PB-208) -ERR-ANALYS (DATA-ERR).Data-Point Reader Uncertainty. - (ERR-T).The Uncertainty is Reported by Authors. -ENDBIB 7 -COMMON 3 3 -ERR-S E-LVL DATA-ERR -1/FM MEV PER-CENT - 0.035 6.43 12. +HISTORY (20110312A) SD: Col. MISC changed on MOM-TR and + col. q - deleted. +ENDBIB 5 +COMMON 1 3 +E-LVL +MEV + 6.43 ENDCOMMON 3 -DATA 4 9 -MOM-TR DATA ERR-T MISC -MEV/C MB/SR PER-CENT MEV/C - 1.69732 0.06400 335. - 1.79865 0.07800 355. - 1.95572 0.08000 386. - 2.06718 0.05700 408. - 2.12798 0.03300 15. 420. - 2.23945 0.02900 15. 442. - 2.35091 0.02040 464. - 2.46745 0.01020 18. 487. - 2.67518 0.00510 21. 528. +DATA 3 9 +MOM-TR DATA DATA-ERR +MEV/C MB/SR PER-CENT + 335. 0.06400 + 355. 0.07800 + 386. 0.08000 + 408. 0.05700 + 420. 0.03300 15. + 442. 0.02900 15. + 464. 0.02040 + 487. 0.01020 18. + 528. 0.00510 21. ENDDATA 11 -ENDSUBENT 27 -SUBENT O0187006 970113 20050926 0000 -BIB 6 7 -REACTION (82-PB-208(P,INL)82-PB-208,PAR,DA,,,EXP) See Fig.13 +ENDSUBENT 25 +SUBENT O0187006 20110312 20111003 20110913 O045 +BIB 5 6 +REACTION (82-PB-208(P,INL)82-PB-208,PAR,DA) See Fig.13 EN-SEC (E-LVL,82-PB-208) LEVEL-PROP (82-PB-208,E-LVL=7.06,SPIN=12.,PARITY=-1.) -MISC-COL (MISC) Linear Momentum Transferred to 208-Pb. -MOM-SEC (MOM-TR,82-PB-208) -ERR-ANALYS (DATA-ERR).Data-Point Reader Uncertainty. - (ERR-T).The Uncertainty is Reported by Authors. -ENDBIB 7 -COMMON 3 3 -ERR-S E-LVL DATA-ERR -1/FM MEV PER-CENT - 0.035 7.06 14. +ERR-ANALYS (DATA-ERR) Nothing said about uncertainties +HISTORY (20110312A) SD: Col. MISC changed on MOM-TR and + col. q - deleted. +ENDBIB 6 +COMMON 1 3 +E-LVL +MEV + 7.06 ENDCOMMON 3 -DATA 4 12 -MOM-TR DATA ERR-T MISC -1/FM MB/SR PER-CENT MEV/C - 1.48959 0.05500 16. 294. - 1.62639 0.06200 15. 321. - 1.73279 0.06300 342. - 1.83919 0.07800 363. - 1.96585 0.09500 388. - 2.07225 0.09700 409. - 2.13305 0.06800 421. - 2.24452 0.04600 443. - 2.36105 0.02500 466. - 2.47758 0.01680 15. 489. - 2.65491 0.00580 18. 524. - 2.76638 0.00410 19. 546. +DATA 3 12 +MOM-TR DATA DATA-ERR +MEV/C MB/SR PER-CENT + 294. 0.05500 16. + 321. 0.06200 15. + 342. 0.06300 + 363. 0.07800 + 388. 0.09500 + 409. 0.09700 + 421. 0.06800 + 443. 0.04600 + 466. 0.02500 + 489. 0.01680 15. + 524. 0.00580 18. + 546. 0.00410 19. ENDDATA 14 -ENDSUBENT 30 +ENDSUBENT 29 ENDENTRY 6 diff --git a/exforall/O02/O0277.x4 b/exforall/O02/O0277.x4 index 94e140165..346ac5ba1 100644 --- a/exforall/O02/O0277.x4 +++ b/exforall/O02/O0277.x4 @@ -1,65 +1,75 @@ -ENTRY O0277 20101223 20110621 20110620 O044 -SUBENT O0277001 20101223 20110621 20110620 O044 -BIB 12 56 +ENTRY O0277 20110313 20111003 20110913 O045 +SUBENT O0277001 20110313 20111003 20110913 O045 +BIB 12 62 TITLE Nuclide production by proton-induced reactions - on elements (6<=Z<=29) in the energy range from 800 + on elements (6<=Z<=29) in the energy range from 800 to 2600 MeV. -AUTHOR (R.Michel, M.Gloris, H.-J.Lange, I.Leya, M.Luepke, - U.Herpers, B.Dittrich-Hannen, R.Roesel, Th.Schiekel, - D.Filges, P.Dragovitsch, M.Suter, H.-J.Hofmann, - W.Woelfli, P.W.Kubik, H.Baur, R.Wieler) +AUTHOR (R.Michel,M.Gloris,H.-J.Lange,I.Leya,M.Luepke, + U.Herpers,B.Dittrich-Hannen,R.Roesel,Th.Schiekel, + D.Filges,P.Dragovitsch,M.Suter,H.-J.Hofmann, + W.Woelfli,P.W.Kubik,H.Baur,R.Wieler) INSTITUTE (2GERKLN,2GERUH ,2GERJUL,1USAFSU,2SWTETH) REFERENCE (J,NIM/B,103,183,1995) -HISTORY (19960704C) - (20101021A).New information in Status code was added. MONITOR (13-AL-27(P,X)11-NA-22,CUM,SIG,,,EVAL) -MONIT-REF (,J.TOBAILEM+,R,CEA-N-1466,1981) +MONIT-REF (,J.Tobailem+,R,CEA-N-1466,1981) FACILITY (MESON,1USALAS) 800 MeV (LINAC,2FR SAC) 1200, 1600 and 2600 MeV. -METHOD (STTA,EXTB,BCINT). The Irradiations with 800, 1200, +METHOD (STTA,EXTB,BCINT). The irradiations with 800, 1200, 1600 and 260 MeV lasted 20400, 39660,43080 and 42540 seconds with beam currents between 1.15 and 1.35 nanoampere. ERR-ANALYS (ERR-T) Absolute uncertainties measurements. - This uncertainty includes: - 1. Uncertainties in the determination of the number of - targets atoms in the beam and their homogeneity over - the target area - 2%. - 2. Impurities in the Target materials causing + This uncertainty Includes: + (ERR-1) 1. Uncertainties in the determination of the + number of targets atoms in the beam and their + homogeneity over the target area - 2%. + 2. Impurities in the target materials causing interfering nuclear reactions and errors resulting from the correction of contributions of other target constituents. - 3. Fluctuation in beam intensity during irradiation: - The beam intensities were continuously monitored and - recorded. The fluctuations and interruptions of the - irradiations were taken into account when calculating - fluxes and cross sections. An analysis of the - uncertainties of this procedure resulted in an overall - error of 2%. - 4. Uncertainties in the correction on influence of - secondary particles. - 5. Uncertainty of measurement of monitoring - radionuclide, Here 22-Na : less 1%. - 6.Error of the absolute calibration of - gamma-spectrometers: less 5% - 7.Dead-time and pile up losses in gamma-spectrometry. - 8.Reproducibility of photopeak integration. - 9.Statistical counting error. - 10. Recoil loss and recoil contamination - these errors - cancel out. - 11. Error of monitor cross section was adopted to be - zero. - 12. Self-absorption of gamma-rays in the sample was - neglected (Except Barium) + (ERR-2) 3. Fluctuation in beam intensity during + irradiation: the beam intensities were continuously + monitored and recorded. The fluctuations and + interruptions of the irradiations were taken into + account when calculating fluxes and cross sections. + An analysis of the uncertainties of this procedure + resulted in an overall error of 2%. + 4. Uncertainties in the correction on influence + of secondary particles. + (ERR-3,,1.) 5. Uncertainty of measurement of monitoring + radionuclide, here 22-Na : <1%. + (ERR-4,,5.) 6.Error of the absolute calibration of + gamma-spectrometers: <5% + 7.Dead-time and pile up losses in + gamma-spectrometry. + 8.Reproducibility of photopeak integration. + 9.Statistical counting error. + 10. Recoil loss and recoil contamination - these + errors cancel out. + 11. Error of monitor cross section was adopted + to be zero. + 12. Self-absorption of gamma-rays in the sample + was neglected (except barium) Consider both the thickness of the target foils and the error introduced by the energy straggling. -ADD-RES (COMP) Semiempirical Formulas, INC/E Model, HETC code. +ADD-RES (COMP) Semiempirical formulas, Inc/E Model, HETC Code. STATUS (TABLE) From R.Michel. (COREL,O1881001) another measurements- for Fe-targets sub.O1881002-025 -ENDBIB 56 -NOCOMMON 0 0 -ENDSUBENT 59 +HISTORY (19960704C) + (19970111U) Last checking has been done. + (20101021A).New information in Status code was added. + (20110313A) SD: Partial uncertainties added + COMMON + section in Subent 001. SF5=IND added to REACTION code + in several Subents (see Subents). In others - cosmetic + changes (such as 10be => 10Be, etc.) +ENDBIB 62 +COMMON 2 3 +ERR-1 ERR-2 +PER-CENT PER-CENT + 2.0 2.0 +ENDCOMMON 3 +ENDSUBENT 69 SUBENT O0277002 970111 20050616 20050926 0000 BIB 5 6 REACTION (6-C-0(P,X)4-BE-7,,SIG) @@ -108,13 +118,13 @@ MEV MB MB 0.160E+04 0.133E+02 0.132E+01 ENDDATA 3 ENDSUBENT 15 -SUBENT O0277005 970111 20050616 20050926 0000 +SUBENT O0277005 20110313 20111003 20110913 O045 BIB 3 5 REACTION (7-N-0(P,X)4-BE-10,,SIG) - Uncertainty is Larger Than C-13 Impurity. Independent. + Uncertainty is larger than C-13 impurity. Independent. METHOD (AMS) -COMMENT -By Authors- The Standard 'S433' with 10be/9-Be Ratio - Of (9.31+-0.23)*10**(-11) Was Used. +COMMENT -By Authors- The Standard 'S433' with 10Be/9-Be ratio + of (9.31+-0.23)*10**(-11) was used. ENDBIB 5 NOCOMMON 0 0 DATA 3 1 @@ -143,14 +153,14 @@ MEV MB MB 2600. 10.6 0.9 ENDDATA 6 ENDSUBENT 18 -SUBENT O0277007 970111 20050616 20050926 0000 +SUBENT O0277007 20110313 20111003 20110913 O045 BIB 3 6 REACTION (8-O-0(P,X)4-BE-10,,SIG) - Uncertainty is Larger Than O-17 and O-18 Impurity. + Uncertainty is larger than O-17 and O-18 impurity. Independent. METHOD (AMS) -COMMENT -By Authors- The Standard 'S433' with 10be/9-Be Ratio - Of (9.31+-0.23)*10**(-11) Was Used. +COMMENT -By Authors- The Standard 'S433' with 10Be/9-Be ratio + Of (9.31+-0.23)*10**(-11) was used. ENDBIB 6 NOCOMMON 0 0 DATA 3 4 @@ -162,15 +172,17 @@ MEV MB MB 2600. 2.76 0.25 ENDDATA 6 ENDSUBENT 17 -SUBENT O0277008 970111 20050616 20050926 0000 -BIB 4 6 -REACTION (12-MG-0(P,X)2-HE-3,,SIG) +SUBENT O0277008 20110313 20111003 20110913 O045 +BIB 5 8 +REACTION (12-MG-0(P,X)2-HE-3,IND,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -COMMENT -By Authors- The Contribution from Decay of H-3 has - Been Subtracted. -ENDBIB 6 +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,TH.Graf+,J,GCA,54,2511,1989) Experim. Technique. +COMMENT -By Authors- The Contribution from decay of H-3 has + been subtracted. +HISTORY (20110313A) SD: SF5=IND added to REACTION code. + See COMMENT +ENDBIB 8 NOCOMMON 0 0 DATA 3 4 EN DATA ERR-T @@ -180,13 +192,13 @@ MEV MB MB 1600. 63.5 4.6 2600. 60.1 4.2 ENDDATA 6 -ENDSUBENT 17 -SUBENT O0277009 970111 20050616 20050926 0000 +ENDSUBENT 19 +SUBENT O0277009 20110313 20111003 20110913 O045 BIB 3 4 REACTION (12-MG-0(P,X)2-HE-4,,SIG) Independent METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,TH.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -216,12 +228,12 @@ MEV MB MB 2600. 10.3 0.8 ENDDATA 6 ENDSUBENT 16 -SUBENT O0277011 970111 20050616 20050926 0000 +SUBENT O0277011 20110313 20111003 20110913 O045 BIB 3 4 REACTION (12-MG-0(P,X)4-BE-10,,SIG) Independent METHOD (AMS) -COMMENT -By Authors- The Standard 'S433' with 10be/9-Be Ratio - Of (9.31+-0.23)*10**(-11) Was Used. +COMMENT -By Authors- The standard 'S433' with 10Be/9-Be ratio + of (9.31+-0.23)*10**(-11) was used. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -233,12 +245,12 @@ MEV MB MB 2600. 3.05 0.28 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277012 970111 20050616 20050926 0000 +SUBENT O0277012 20110313 20111003 20110913 O045 BIB 3 4 REACTION (12-MG-0(P,X)10-NE-20,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.WIELER+,J,GCA,53,1449,1989) Experim. Technique. + (I,,TH.GRAF+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -250,12 +262,12 @@ MEV MB MB 2600. 20.7 1.4 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277013 970111 20050616 20050926 0000 +SUBENT O0277013 20110313 20111003 20110913 O045 BIB 3 4 REACTION (12-MG-0(P,X)10-NE-21,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,TH.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -267,12 +279,12 @@ MEV MB MB 2600. 21.9 1.0 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277014 970111 20050616 20050926 0000 +SUBENT O0277014 20110313 20111003 20110913 O045 BIB 3 4 REACTION (12-MG-0(P,X)10-NE-22,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,TH.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -284,15 +296,17 @@ MEV MB MB 2600. 34.8 2.0 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277015 970111 20050616 20050926 0000 -BIB 4 6 -REACTION (12-MG-0(P,X)10-NE-22,,SIG) +SUBENT O0277015 20110313 20111003 20110913 O045 +BIB 5 8 +REACTION (12-MG-0(P,X)10-NE-22,IND,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -COMMENT -By Authors- The Contribution from Decay of Na-22 has - Been Subtracted. -ENDBIB 6 +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,TH.Graf+,J,GCA,54,2511,1989) Experim. Technique. +COMMENT -By Authors- The contribution from decay of Na-22 has + been subtracted. +HISTORY (20110313A) SD: SF5=IND added to REACTION code. + See COMMENT +ENDBIB 8 NOCOMMON 0 0 DATA 3 4 EN DATA ERR-T @@ -302,7 +316,7 @@ MEV MB MB 0.160E+04 0.152E+02 0.119E+01 0.260E+04 0.109E+02 0.137E+01 ENDDATA 6 -ENDSUBENT 17 +ENDSUBENT 19 SUBENT O0277016 970111 20050616 20050926 0000 BIB 5 5 REACTION (12-MG-0(P,X)11-NA-22,CUM,SIG) @@ -338,15 +352,17 @@ MEV MB MB 2600. 5.96 0.49 ENDDATA 5 ENDSUBENT 15 -SUBENT O0277018 970111 20050616 20050926 0000 -BIB 4 6 -REACTION (13-AL-27(P,X)2-HE-3,,SIG) +SUBENT O0277018 20110313 20111003 20110913 O045 +BIB 5 8 +REACTION (13-AL-27(P,X)2-HE-3,IND,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -COMMENT -By Authors- The Contribution from Decay of H-3 has - Been Subtracted. -ENDBIB 6 +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. +COMMENT -By Authors- The contribution from decay of H-3 has + been subtracted. +HISTORY (20110313A) SD: SF5=IND added to REACTION code. + See COMMENT +ENDBIB 8 NOCOMMON 0 0 DATA 3 4 EN DATA ERR-T @@ -356,13 +372,13 @@ MEV MB MB 1600. 68.5 5.0 2600. 63.2 4.4 ENDDATA 6 -ENDSUBENT 17 -SUBENT O0277019 970111 20050616 20050926 0000 +ENDSUBENT 19 +SUBENT O0277019 20110313 20111003 20110913 O045 BIB 3 4 REACTION (13-AL-27(P,X)2-HE-4,,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -374,14 +390,14 @@ MEV MB MB 2600. 430. 18. ENDDATA 6 ENDSUBENT 15 -SUBENT O0277020 970111 20050616 20050926 0000 +SUBENT O0277020 20110313 20111003 20110913 O045 BIB 6 6 REACTION (13-AL-27(P,X)4-BE-7,,SIG) METHOD (ACTIV) ANALYSIS (AREA) DECAY-DATA (4-BE-7,53.3D,DG,477.,0.104) DETECTOR (GELI). -MISC-COL (MISC) Data from Cea-N-1466. +MISC-COL (MISC) Data from CEA-N-1466. ENDBIB 6 NOCOMMON 0 0 DATA 4 4 @@ -393,12 +409,12 @@ MEV MB MB MB 2600. 9.50 0.72 8.8 ENDDATA 6 ENDSUBENT 17 -SUBENT O0277021 970111 20050616 20050926 0000 +SUBENT O0277021 20110313 20111003 20110913 O045 BIB 3 4 REACTION (13-AL-27(P,X)4-BE-10,,SIG) METHOD (AMS) -COMMENT -By Authors- The Standard 'S433' with 10be/9-Be Ratio - Of (9.31+-0.23)*10**(-11) Was Used. +COMMENT -By Authors- The standard 'S433' with 10Be/9-Be ratio + of (9.31+-0.23)*10**(-11) was used. ENDBIB 4 NOCOMMON 0 0 DATA 3 3 @@ -409,12 +425,12 @@ MEV MB MB 2600. 3.32 0.31 ENDDATA 5 ENDSUBENT 14 -SUBENT O0277022 970111 20050616 20050926 0000 +SUBENT O0277022 20110313 20111003 20110913 O045 BIB 3 4 REACTION (13-AL-27(P,X)10-NE-20,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -426,12 +442,12 @@ MEV MB MB 2600. 21.9 1.4 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277023 970111 20050616 20050926 0000 +SUBENT O0277023 20110313 20111003 20110913 O045 BIB 3 4 REACTION (13-AL-27(P,X)10-NE-21,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -443,13 +459,14 @@ MEV MB MB 2600. 22.6 1.0 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277024 970111 20050616 20050926 0000 -BIB 3 4 -REACTION (13-AL-27(P,2N+4P)10-NE-22,CUM,SIG) +SUBENT O0277024 20110313 20111003 20110913 O045 +BIB 4 5 +REACTION (13-AL-27(P,X)10-NE-22,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -ENDBIB 4 +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. +HISTORY (20110313A) SD: SF3 changed in REACTION code: 2N+4P->X +ENDBIB 5 NOCOMMON 0 0 DATA 3 4 EN DATA ERR-T @@ -459,16 +476,18 @@ MEV MB MB 1600. 28.3 2.1 2600. 24.9 0.7 ENDDATA 6 -ENDSUBENT 15 -SUBENT O0277025 970111 20050616 20050926 0000 -BIB 4 6 -REACTION (13-AL-27(P,X)10-NE-22,,SIG) -COMMENT -By Authors- The Contribution from Decay of Na-22 has - Been Subtracted. +ENDSUBENT 16 +SUBENT O0277025 20110313 20111003 20110913 O045 +BIB 5 8 +REACTION (13-AL-27(P,X)10-NE-22,IND,SIG) +COMMENT -By Authors- The contribution from decay of Na-22 has + been subtracted. METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -ENDBIB 6 +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. +HISTORY (20110313A) SD: SF5=IND added to REACTION code. + See COMMENT +ENDBIB 8 NOCOMMON 0 0 DATA 3 4 EN DATA ERR-T @@ -478,15 +497,15 @@ MEV MB MB 1600. 15.1 1.1 2600. 12.6 0.7 ENDDATA 6 -ENDSUBENT 17 -SUBENT O0277026 970111 20050616 20050926 0000 +ENDSUBENT 19 +SUBENT O0277026 20110313 20111003 20110913 O045 BIB 6 6 REACTION (13-AL-27(P,X)11-NA-22,CUM,SIG) METHOD (ACTIV) ANALYSIS (AREA) DECAY-DATA (11-NA-22,2.60YR,DG,1274.,0.999) DETECTOR (GELI). -MISC-COL (MISC) Datum from Cea-N-1466 of Tobailem. +MISC-COL (MISC) Datum from CEA-N-1466 of Tobailem. ENDBIB 6 NOCOMMON 0 0 DATA 4 4 @@ -498,14 +517,14 @@ MEV MB MB MB 2600. 12.1 0.9 11.7 ENDDATA 6 ENDSUBENT 17 -SUBENT O0277027 970111 20050616 20050926 0000 +SUBENT O0277027 20110313 20111003 20110913 O045 BIB 6 6 REACTION (13-AL-27(P,X)11-NA-24,CUM,SIG) METHOD (ACTIV) ANALYSIS (AREA) DECAY-DATA (11-NA-24,14.9HR,DG,1368.,1.0) DETECTOR (GELI). -MISC-COL (MISC) Data from Cea-N-1466 of Tobailem. +MISC-COL (MISC) Data from CEA-N-1466 of Tobailem. ENDBIB 6 NOCOMMON 0 0 DATA 4 4 @@ -537,15 +556,17 @@ MEV MB MB 2600. 19.1 1.9 ENDDATA 5 ENDSUBENT 18 -SUBENT O0277029 970111 20050616 20050926 0000 -BIB 4 6 -REACTION (14-SI-0(P,X)2-HE-3,,SIG) +SUBENT O0277029 20110313 20111003 20110913 O045 +BIB 5 8 +REACTION (14-SI-0(P,X)2-HE-3,IND,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -COMMENT -By Authors- The Contribution from Decay of H-3 has - Been Subtracted. -ENDBIB 6 +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. +COMMENT -By Authors- The contribution from decay of H-3 has + been subtracted. +HISTORY (20110313A) SD: SF5=IND added to REACTION code. + See COMMENT +ENDBIB 8 NOCOMMON 0 0 DATA 3 4 EN DATA ERR-T @@ -555,13 +576,13 @@ MEV MB MB 1600. 79.0 5.8 2600. 69.9 4.9 ENDDATA 6 -ENDSUBENT 17 -SUBENT O0277030 970111 20050616 20050926 0000 +ENDSUBENT 19 +SUBENT O0277030 20110313 20111003 20110913 O045 BIB 3 4 REACTION (14-SI-0(P,X)2-HE-4,,SIG) Independent. METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -591,12 +612,12 @@ MEV MB MB 2600. 11.2 0.8 ENDDATA 6 ENDSUBENT 16 -SUBENT O0277032 970111 20050616 20050926 0000 +SUBENT O0277032 20110313 20111003 20110913 O045 BIB 3 4 REACTION (14-SI-0(P,X)4-BE-10,,SIG) Independent. METHOD (AMS) -COMMENT -By Authors- The Standard 'S433' with 10be/9-Be Ratio - Of (9.31+-0.23)*10**(-11) Was Used. +COMMENT -By Authors- The standard 'S433' with 10Be/9-Be ratio + of (9.31+-0.23)*10**(-11) was used. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -608,12 +629,12 @@ MEV MB MB 2600. 2.47 0.23 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277033 970111 20050616 20050926 0000 +SUBENT O0277033 20110313 20111003 20110913 O045 BIB 3 4 REACTION (14-SI-0(P,X)10-NE-20,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -625,12 +646,12 @@ MEV MB MB 2600. 17.6 1.1 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277034 970111 20050616 20050926 0000 +SUBENT O0277034 20110313 20111003 20110913 O045 BIB 3 4 REACTION (14-SI-0(P,X)10-NE-21,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -642,12 +663,12 @@ MEV MB MB 2600. 16.1 0.7 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277035 970111 20050616 20050926 0000 +SUBENT O0277035 20110313 20111003 20110913 O045 BIB 3 4 REACTION (14-SI-0(P,X)10-NE-22,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -659,15 +680,17 @@ MEV MB MB 2600. 19.6 0.2 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277036 970111 20050616 20050926 0000 -BIB 4 6 -REACTION (14-SI-0(P,X)10-NE-22,,SIG) -COMMENT -By Authors- The Contribution from Decay of Na-22 has - Been Subtracted. +SUBENT O0277036 20110313 20111003 20110913 O045 +BIB 5 8 +REACTION (14-SI-0(P,X)10-NE-22,IND,SIG) +COMMENT -By Authors- The contribution from decay of Na-22 has + been subtracted. METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -ENDBIB 6 +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. +HISTORY (20110313A) SD: SF5=IND added to REACTION code. + See COMMENT +ENDBIB 8 NOCOMMON 0 0 DATA 3 4 EN DATA ERR-T @@ -677,7 +700,7 @@ MEV MB MB 1600. 10.5 0.8 2600. 6.08 0.79 ENDDATA 6 -ENDSUBENT 17 +ENDSUBENT 19 SUBENT O0277037 970111 20050616 20050926 0000 BIB 5 5 REACTION (14-SI-0(P,X)11-NA-22,CUM,SIG) @@ -901,12 +924,12 @@ MEV MB MB 2600. 8.30 0.69 ENDDATA 6 ENDSUBENT 16 -SUBENT O0277049 970111 20050616 20050926 0000 +SUBENT O0277049 20110313 20111003 20110913 O045 BIB 3 4 REACTION (22-TI-0(P,X)4-BE-10,,SIG) Independent METHOD (AMS) -COMMENT -By Authors- The Standard 'S433' with 10be/9-Be Ratio - Of (9.31+-0.23)*10**(-11) Was Used. +COMMENT -By Authors- The standard 'S433' with 10Be/9-Be ratio + of (9.31+-0.23)*10**(-11) was used. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -1465,12 +1488,12 @@ MEV MB MB 2600. 8.92 0.90 ENDDATA 6 ENDSUBENT 16 -SUBENT O0277078 970111 20050616 20050926 0000 +SUBENT O0277078 20110313 20111003 20110913 O045 BIB 3 4 REACTION (25-MN-55(P,X)4-BE-10,,SIG) METHOD (AMS) -COMMENT -By Authors- The Standard 'S433' with 10be/9-Be Ratio - Of (9.31+-0.23)*10**(-11) Was Used. +COMMENT -By Authors- The standard 'S433' with 10Be/9-Be ratio + of (9.31+-0.23)*10**(-11) was used. ENDBIB 4 NOCOMMON 0 0 DATA 3 3 @@ -1749,15 +1772,17 @@ MEV MB MB 2600. 22.2 2.7 ENDDATA 6 ENDSUBENT 16 -SUBENT O0277093 970111 20050616 20050926 0000 -BIB 4 6 -REACTION (26-FE-0(P,X)2-HE-3,,SIG) +SUBENT O0277093 20110313 20111003 20110913 O045 +BIB 5 8 +REACTION (26-FE-0(P,X)2-HE-3,IND,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -COMMENT -By Authors- The Contribution from Decay of H-3 has - Been Subtracted. -ENDBIB 6 +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. +COMMENT -By Authors- The contribution from decay of H-3 has + been subtracted. +HISTORY (20110313A) SD: SF5=IND added to REACTION code. + See COMMENT +ENDBIB 8 NOCOMMON 0 0 DATA 3 5 EN DATA ERR-T @@ -1768,13 +1793,13 @@ MEV MB MB 1600. 99.8 7.4 2600. 91.8 6.6 ENDDATA 7 -ENDSUBENT 18 -SUBENT O0277094 970111 20050616 20050926 0000 +ENDSUBENT 20 +SUBENT O0277094 20110313 20111003 20110913 O045 BIB 3 4 REACTION (26-FE-0(P,X)2-HE-4,,SIG) Independent. METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 5 @@ -1805,12 +1830,12 @@ MEV MB MB 2600. 10.4 0.8 ENDDATA 6 ENDSUBENT 16 -SUBENT O0277096 970111 20050616 20050926 0000 +SUBENT O0277096 20110313 20111003 20110913 O045 BIB 3 4 REACTION (26-FE-0(P,X)4-BE-10,,SIG) Independent. METHOD (AMS) -COMMENT -By Authors- The Standard 'S433' with 10be/9-Be Ratio - Of (9.31+-0.23)*10**(-11) Was Used. +COMMENT -By Authors- The standard 'S433' with 10Be/9-Be ratio + of (9.31+-0.23)*10**(-11) was used. ENDBIB 4 NOCOMMON 0 0 DATA 3 3 @@ -1821,12 +1846,12 @@ MEV MB MB 2600. 4.22 0.39 ENDDATA 5 ENDSUBENT 14 -SUBENT O0277097 970111 20050616 20050926 0000 +SUBENT O0277097 20110313 20111003 20110913 O045 BIB 3 4 REACTION (26-FE-0(P,X)10-NE-20,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 1 @@ -1835,12 +1860,12 @@ MEV MB MB 2600. 6.11 4.3 ENDDATA 3 ENDSUBENT 12 -SUBENT O0277098 970111 20050616 20050926 0000 +SUBENT O0277098 20110313 20111003 20110913 O045 BIB 3 4 REACTION (26-FE-0(P,X)10-NE-21,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -1852,12 +1877,12 @@ MEV MB MB 2600. 5.89 0.42 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277099 970111 20050616 20050926 0000 +SUBENT O0277099 20110313 20111003 20110913 O045 BIB 3 4 REACTION (26-FE-0(P,X)10-NE-22,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 1 @@ -1866,22 +1891,24 @@ MEV MB MB 2600. 12.6 0.9 ENDDATA 3 ENDSUBENT 12 -SUBENT O0277100 970111 20050616 20050926 0000 -BIB 4 6 -REACTION (26-FE-0(P,X)10-NE-22,,SIG) -COMMENT -By Authors- The Contribution from Decay of Na-22 has - Been Subtracted. +SUBENT O0277100 20110313 20111003 20110913 O045 +BIB 5 8 +REACTION (26-FE-0(P,X)10-NE-22,IND,SIG) +COMMENT -By Authors- The contribution from decay of Na-22 has + been subtracted. METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -ENDBIB 6 +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. +HISTORY (20110313A) SD: SF5=IND added to REACTION code. + See COMMENT +ENDBIB 8 NOCOMMON 0 0 DATA 3 1 EN DATA ERR-T MEV MB MB 2600. 9.36 0.66 ENDDATA 3 -ENDSUBENT 14 +ENDSUBENT 16 SUBENT O0277101 970111 20050616 20050926 0000 BIB 5 5 REACTION (26-FE-0(P,X)11-NA-22,CUM,SIG) @@ -1973,12 +2000,12 @@ MEV MB MB 2600. 10.4 1.4 ENDDATA 5 ENDSUBENT 14 -SUBENT O0277106 970111 20050616 20050926 0000 +SUBENT O0277106 20110313 20111003 20110913 O045 BIB 3 4 REACTION (26-FE-0(P,X)18-AR-36,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 1 @@ -1987,12 +2014,12 @@ MEV MB MB 2600. 1.02 0.07 ENDDATA 3 ENDSUBENT 12 -SUBENT O0277107 970111 20050616 20050926 0000 +SUBENT O0277107 20110313 20111003 20110913 O045 BIB 3 4 REACTION (26-FE-0(P,X)18-AR-38,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 5 @@ -2738,15 +2765,17 @@ MEV MB MB 2600. 0.069 0.010 ENDDATA 6 ENDSUBENT 19 -SUBENT O0277145 970111 20050616 20050926 0000 -BIB 4 6 -REACTION (28-NI-0(P,X)2-HE-3,,SIG) +SUBENT O0277145 20110313 20111003 20110913 O045 +BIB 5 8 +REACTION (28-NI-0(P,X)2-HE-3,IND,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -COMMENT -By Authors- The Contribution from Decay of H-3 has - Been Subtracted. -ENDBIB 6 +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. +COMMENT -By Authors- The contribution from decay of H-3 has + been subtracted. +HISTORY (20110313A) SD: SF5=IND added to REACTION code. + See COMMENT +ENDBIB 8 NOCOMMON 0 0 DATA 3 4 EN DATA ERR-T @@ -2756,13 +2785,13 @@ MEV MB MB 1600. 110. 8. 2600. 144. 10. ENDDATA 6 -ENDSUBENT 17 -SUBENT O0277146 970111 20050616 20050926 0000 +ENDSUBENT 19 +SUBENT O0277146 20110313 20111003 20110913 O045 BIB 3 4 REACTION (28-NI-0(P,X)2-HE-4,,SIG) Independent. METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -2792,12 +2821,12 @@ MEV MB MB 2600. 13.0 1.1 ENDDATA 6 ENDSUBENT 16 -SUBENT O0277148 970111 20050616 20050926 0000 +SUBENT O0277148 20110313 20111003 20110913 O045 BIB 3 4 REACTION (28-NI-0(P,X)4-BE-10,,SIG) Independent. METHOD (AMS) -COMMENT -By Authors- The Standard 'S433' with 10be/9-Be Ratio - Of (9.31+-0.23)*10**(-11) Was Used. +COMMENT -By Authors- The standard 'S433' with 10Be/9-Be ratio + of (9.31+-0.23)*10**(-11) was used. ENDBIB 4 NOCOMMON 0 0 DATA 3 3 @@ -2808,12 +2837,12 @@ MEV MB MB 2600. 3.37 0.28 ENDDATA 5 ENDSUBENT 14 -SUBENT O0277149 970111 20050616 20050926 0000 +SUBENT O0277149 20110313 20111003 20110913 O045 BIB 3 4 REACTION (28-NI-0(P,X)10-NE-20,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 3 @@ -2824,12 +2853,12 @@ MEV MB MB 2600. 6.8 1.0 ENDDATA 5 ENDSUBENT 14 -SUBENT O0277150 970111 20050616 20050926 0000 +SUBENT O0277150 20110313 20111003 20110913 O045 BIB 3 4 REACTION (28-NI-0(P,X)10-NE-21,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 @@ -2841,15 +2870,15 @@ MEV MB MB 2600. 7.24 0.38 ENDDATA 6 ENDSUBENT 15 -SUBENT O0277151 970111 20050616 20050926 0000 +SUBENT O0277151 20110313 20111003 20110913 O045 BIB 4 7 REACTION (28-NI-0(P,X)10-NE-22,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -FLAG (1.). Original Paper has Misprint For Datum - Uncertainty. This Misprint is Corrected According to - Data Tables Which have Been Received from R.Michel. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. +FLAG (1.). Original paper has misprint for datum + uncertainty. This misprint is corrected according to + data tables which have been received from R.Michel. ENDBIB 7 NOCOMMON 0 0 DATA 4 3 @@ -2860,15 +2889,17 @@ MEV MB MB NO-DIM 2600. 7.67 0.48 1. ENDDATA 5 ENDSUBENT 17 -SUBENT O0277152 970111 20050616 20050926 0000 -BIB 4 6 -REACTION (28-NI-0(P,X)10-NE-22,,SIG) -COMMENT -By Authors- The Contribution from Decay of Na-22 has - Been Subtracted. +SUBENT O0277152 20110313 20111003 20110913 O045 +BIB 5 8 +REACTION (28-NI-0(P,X)10-NE-22,IND,SIG) +COMMENT -By Authors- The contribution from decay of Na-22 has + been subtracted. METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. -ENDBIB 6 +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. +HISTORY (20110313A) SD: SF5=IND added to REACTION code. + See COMMENT +ENDBIB 8 NOCOMMON 0 0 DATA 3 3 EN DATA ERR-T @@ -2877,7 +2908,7 @@ MEV MB MB 1200. 2.02 0.19 2600. 4.09 0.39 ENDDATA 5 -ENDSUBENT 16 +ENDSUBENT 18 SUBENT O0277153 970111 20050616 20050926 0000 BIB 5 5 REACTION (28-NI-0(P,X)11-NA-22,CUM,SIG) @@ -2948,12 +2979,12 @@ MEV MB MB 1200. 9.30 0.75 ENDDATA 4 ENDSUBENT 13 -SUBENT O0277157 970111 20050616 20050926 0000 +SUBENT O0277157 20110313 20111003 20110913 O045 BIB 3 4 REACTION (28-NI-0(P,X)18-AR-36,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 3 @@ -2964,12 +2995,12 @@ MEV MB MB 2600. 2.81 0.20 ENDDATA 5 ENDSUBENT 14 -SUBENT O0277158 970111 20050616 20050926 0000 +SUBENT O0277158 20110313 20111003 20110913 O045 BIB 3 4 REACTION (28-NI-0(P,X)18-AR-38,CUM,SIG) METHOD (ASEP) -REL-REF (N,,R.WIELER+,J,GCA,53,1449,89) Experimental Technique. - (N,,TH.GRAF+,J,GCA,54,2511,89) Experimental Technique. +REL-REF (I,,R.Wieler+,J,GCA,53,1449,1989) Experim. Technique. + (I,,Th.Graf+,J,GCA,54,2511,1989) Experim. Technique. ENDBIB 4 NOCOMMON 0 0 DATA 3 4 diff --git a/exforall/O03/O0395.x4 b/exforall/O03/O0395.x4 index 729b2e621..b6e53cf3b 100644 --- a/exforall/O03/O0395.x4 +++ b/exforall/O03/O0395.x4 @@ -1,585 +1,27 @@ -ENTRY O0395 970707 20050926 0000 -SUBENT O0395001 970707 20050926 0000 -BIB 15 40 +ENTRY O0395 20110711 20111003 20110913 O045 +SUBENT O0395001 20110711 20111003 20110913 O045 +BIB 6 16 TITLE Proton Scattering Off 9-Be and the Final-State - Interection in (E,E'P) And (G,P) Reactions on 10-B. -AUTHOR (L.J.DE BEVER, H.P.BLOK, J.BLOUW, M.FUJIWARA, K.HOSONO, - J.J.KELLY, S.KUWAMOTO, L.LAPIKAS, G.VAN DER STEENHOVEN, - K.TAKAHISA, J.TAKAMATSU, M.YOSOI) + Interaction in (e,e'p) and (gamma,p) Reactions on 10-B +AUTHOR (L.J.de Bever, H.P.Blok, J.Blouw, M.Fujiwara, K.Hosono, + J.J.Kelly, S.Kuwamoto, L.Lapikas, G.van der Steenhoven, + K.Takahisa, J.Takamatsu, M.Yosoi) +REFERENCE (J,NP/A,579,13,1994) +FACILITY (CYCLO,2JPNOSA).AVF Cyclotron of the Research Center + For Nuclear Physics, Osaka University. INSTITUTE (2JPNOSA) (2NEDIKO) (2NEDFUL) (2JPNKTO) (2JPNTOH) (1USAMRY) -HISTORY (970701C) - (970707U) Last checking has been done. -REFERENCE (J,NP/A,579,13,94) -REL-REF (N,,M.KONDO+,C,75ZUERI,,95,75) - (N,,H.IKEGANU+,J,NIM,175,335,80) - (N,,Y.FIJUTA+,J,NIM,225,298,84) - The Details of Measurement Devices. -FACILITY (CYCLO,2JPNOSA).Avf Cyclotron of the Research Center - For Nuclear Physics,Osaka University. -INC-SOURCE (POLIS,LAMB).The Polarized Proton Beam (OF 10 KEV - ENERGY) From the Atomic Beam Type Polarized Ion Source. -METHOD (BCINT) -PART-DET (P) -DETECTOR (MAGSP) The Scattered Protons were Recorded by the - Magnetic Spectrograph (RAIDEN). - The Detection System of this Spectrograph Consists of - A Two-Dimensional Focal Plane Counter with Induction - Readout, a Delta-E Gas Proportional Counter and an - Plastic Scintillator. -ERR-ANALYS (EN-ERR) Upper Limut of the Uncertainty of Beam Energy. - (ERR-5) Upper Limit of Inefficiencies Uncertainty. - (ERR-6) Beam Charge Integration Uncertainty. - (ERR-T) This Uncertainty is Shown in Data Tables. -ADD-RES (COMP). Optical Model. - (POT) -MISC-COL (MISC1) Scattering Angle in Lab.System. - (MISC2) Wave Number of Transfered Linear Momentum. -STATUS (TABLE) The Data were Received from Nea Data Bank. - This is a Part of B.Clark Library. -ENDBIB 40 -COMMON 3 3 -EN-ERR ERR-5 ERR-6 -PER-CENT PER-CENT PER-CENT - 0.1 1. 3. -ENDCOMMON 3 -ENDSUBENT 47 -SUBENT O0395002 970707 20050926 0000 -BIB 2 17 -REACTION S(4-BE-9(P,EL)4-BE-9,,DA,,,EXP) - A(4-BE-9(P,EL)4-BE-9,,POL/DA,,ANA,EXP) -ERR-ANALYS (ERR-1) Upper Limit of Systematic Uncertainty of - Scattered Proton Energy For Forward Directions. - (ERR-2) Systematic Incertainty of Scattered Proton - Energy For Backward Directions. - (ERR-3) Systematic Uncertainty of Scattering Angle For - Forward Directions. - (ERR-4) Systematic Uncertainty of Scattering Angle For - Backward Directions. - (ERR-7) Solid Angle Uncertainty For Forward Directions. - (ERR-8) Solid Angle Uncertainty For Backward - Directions. - (ERR-9) Target Thickness Uncertainty For Forward - Directions. - (ERR-10) Target Thickness Uncertainty For Backward - Directions. -ENDBIB 17 -COMMON 9 6 -EN ERR-2 ERR-3 ERR-4 ERR-7 ERR-8 -ERR-9 ERR-1 ERR-10 -MEV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT -PER-CENT PER-CENT PER-CENT - 54.7 0.5 1. 0.5 2. 1. - 3. 0.5 2. -ENDCOMMON 6 -DATA 7 53 -ANG-CM DATA SDATA AERR-T SERR-T AMISC1 -MISC2 -ADEG MB/SR NO-DIM MB/SR NO-DIM ADEG -1/FM - 11.17 414.6 0.088 4.93374 0.014 10. - 0.287 - 13.96 386.1 0.064 4.51737 0.014 12.5 - 0.358 - 16.74 332. 0.04 3.32 0.016 15. - 0.429 - 16.74 340.4 0.049 4.4252 0.011 15. - 0.429 - 19.53 273.1 0.062 2.13018 0.008 17.5 - 0.5 - 22.3 204.8 0.048 1.92512 0.01 20. - 0.57 - 25.08 151.2 0.049 1.25496 0.009 22.5 - 0.64 - 27.85 104.9 0.042 0.87067 0.009 25. - 0.709 - 30.61 68.47 0.028 0.47244 0.006 27.5 - 0.778 - 33.37 43.14 0.033 0.37532 0.009 30. - 0.846 - 36.12 26.17 0.023 0.24862 0.01 32.5 - 0.914 - 38.86 15.74 0.011 0.20305 0.013 35. - 0.98 - 38.86 15.95 0.016 0.17545 0.013 35. - 0.98 - 38.86 16.33 0.027 0.16493 0.013 35. - 0.98 - 38.86 16.79 0.028 0.18301 0.012 35. - 0.98 - 38.86 16.93 0.029 0.193 0.015 35. - 0.98 - 38.86 16.99 0.03 0.19708 0.013 35. - 0.98 - 38.86 17.02 0.035 0.21956 0.013 35. - 0.98 - 38.86 17.15 0.039 0.21609 0.013 35. - 0.98 - 38.86 17.17 0.04 0.19574 0.011 35. - 0.98 - 38.86 17.32 0.043 0.18186 0.015 35. - 0.98 - 38.86 17.35 0.005 0.19259 0.012 35. - 0.98 - 38.86 17.37 0.05 0.19976 0.012 35. - 0.98 - 38.86 17.49 0.056 0.19939 0.013 35. - 0.98 - 38.86 17.68 -0.02 0.19448 0.016 35. - 0.98 - 41.6 9.826 0.067 0.11595 0.014 37.5 - 1.047 - 44.33 5.897 0.186 0.07607 0.015 39.99 - 1.112 - 47.05 3.95 0.321 0.05056 0.015 42.49 - 1.176 - 49.76 2.94 0.479 0.03557 0.013 44.99 - 1.24 - 52.46 2.504 0.604 0.03205 0.014 47.49 - 1.303 - 55.16 2.32 0.649 0.0283 0.013 49.99 - 1.364 - 57.84 2.121 0.663 0.02503 0.012 52.49 - 1.425 - 60.51 1.948 0.632 0.02162 0.011 54.99 - 1.485 - 63.18 1.764 0.612 0.02046 0.012 57.49 - 1.544 - 65.83 1.533 0.564 0.01886 0.007 59.99 - 1.601 - 65.83 1.557 0.575 0.01168 0.013 59.99 - 1.601 - 68.47 1.32 0.544 0.01399 0.012 62.49 - 1.658 - 71.1 1.069 0.473 0.01016 0.01 64.99 - 1.713 - 73.71 0.8822 0.431 0.009 0.011 67.49 - 1.768 - 76.32 0.7337 0.37 0.00778 0.012 69.99 - 1.821 - 78.91 0.5899 0.324 0.00678 0.013 72.49 - 1.873 - 81.49 0.4671 0.26 0.00556 0.014 74.99 - 1.924 - 84.06 0.3787 0.208 0.00496 0.015 77.49 - 1.973 - 86.62 0.3116 0.153 0.00393 0.015 79.99 - 2.022 - 89.16 0.2547 0.086 0.00354 0.016 82.49 - 2.069 - 91.69 0.2028 -0.001 0.00282 0.016 84.99 - 2.115 - 94.21 0.1751 -0.045 0.00261 0.018 87.49 - 2.159 - 96.72 0.1535 -0.103 0.00243 0.019 89.99 - 2.202 - 99.21 0.1245 -0.136 0.00225 0.022 92.49 - 2.244 - 101.69 0.1087 -0.162 0.00202 0.023 94.99 - 2.285 - 104.15 0.09612 -0.192 0.0019 0.024 97.49 - 2.325 - 106.61 0.0817 -0.187 0.00173 0.026 99.99 - 2.363 - 109.05 0.0691 -0.186 0.00115 0.02 102.49 - 2.4 -ENDDATA 110 -ENDSUBENT 139 -SUBENT O0395003 970707 20050926 0000 -BIB 2 17 -REACTION S(4-BE-9(P,EL)4-BE-9,,DA,,,EXP) - A(4-BE-9(P,EL)4-BE-9,,POL/DA,,ANA,EXP) -ERR-ANALYS (ERR-1) Upper Limit of Systematic Uncertainty of - Scattered Proton Energy For Forward Directions. - (ERR-2) Systematic Incertainty of Scattered Proton - Energy For Backward Directions. - (ERR-3) Systematic Uncertainty of Scattering Angle For - Forward Directions. - (ERR-4) Systematic Uncertainty of Scattering Angle For - Backward Directions. - (ERR-7) Solid Angle Uncertainty For Forward Directions. - (ERR-8) Solid Angle Uncertainty For Backward - Directions. - (ERR-9) Target Thickness Uncertainty For Forward - Directions. - (ERR-10) Target Thickness Uncertainty For Backward - Directions. -ENDBIB 17 -COMMON 9 6 -EN ERR-2 ERR-3 ERR-4 ERR-7 ERR-8 -ERR-9 ERR-1 ERR-10 -MEV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT -PER-CENT PER-CENT PER-CENT - 74.72 2. 1.5 0.5 2.5 1.5 - 3. 1. 1. -ENDCOMMON 6 -DATA 7 45 -ANG-CM DATA SDATA AERR-T SERR-T AMISC1 -MISC2 -ADEG MB/SR NO-DIM MB/SR NO-DIM ADEG -1/FM - 11.19 343.4 0.123 3.98344 0.014 10. - 0.337 - 13.99 299.3 0.112 3.53174 0.014 12.5 - 0.421 - 16.77 245.7 0.125 12.08844 0.062 15. - 0.504 - 19.56 178.2 0.179 4.2768 0.029 17.5 - 0.587 - 22.35 122.3 0.129 5.07545 0.049 20. - 0.67 - 25.13 81.45 0.167 1.38465 0.02 22.5 - 0.752 - 27.9 49.45 0.165 0.49945 0.011 25. - 0.833 - 27.9 52.53 0.172 0.56732 0.012 25. - 0.833 - 30.67 26.38 0.191 0.27435 0.012 27.5 - 0.914 - 33.43 16.42 0.189 0.14778 0.01 29.99 - 0.994 - 36.18 8.937 0.223 0.10188 0.013 32.5 - 1.074 - 38.93 4.981 0.291 0.06027 0.014 34.99 - 1.152 - 41.67 3.169 0.368 0.04246 0.016 37.49 - 1.23 - 44.41 2.207 0.489 0.02759 0.014 39.99 - 1.307 - 47.13 1.761 0.559 0.0236 0.015 42.49 - 1.382 - 49.84 1.472 0.571 0.02061 0.017 44.99 - 1.457 - 49.84 1.495 0.585 0.02855 0.015 44.99 - 1.457 - 49.84 1.548 0.614 0.02028 0.023 44.99 - 1.457 - 52.55 1.362 0.567 0.01839 0.015 47.49 - 1.531 - 55.25 1.141 0.565 0.01301 0.013 49.99 - 1.603 - 55.25 1.144 0.568 0.01636 0.016 49.99 - 1.603 - 57.93 0.9684 0.533 0.01123 0.013 52.49 - 1.675 - 60.61 0.7808 0.502 0.00992 0.015 54.99 - 1.745 - 63.27 0.6217 0.437 0.00808 0.015 57.49 - 1.814 - 65.93 0.4784 0.4 0.00689 0.017 59.99 - 1.881 - 68.44 0.3868 0.295 0.00406 0.013 62.36 - 1.944 - 68.44 0.3898 0.305 0.00347 0.01 62.36 - 1.944 - 68.44 0.3901 0.32 0.00374 0.011 62.36 - 1.944 - 68.57 0.3677 0.281 0.00537 0.017 62.49 - 1.948 - 71.06 0.2831 0.227 0.00306 0.012 64.86 - 2.009 - 73.67 0.2216 0.14 0.00228 0.012 67.35 - 2.073 - 76.27 0.1736 0.032 0.00193 0.013 69.84 - 2.135 - 78.86 0.1304 -0.05 0.00134 0.012 72.33 - 2.196 - 81.43 0.1032 -0.106 0.00103 0.011 74.82 - 2.255 - 83.99 0.08136 -0.188 0.00091 0.013 77.32 - 2.313 - 86.54 0.06983 -0.218 0.00078 0.013 79.81 - 2.37 - 89.08 0.0563 -0.218 0.00069 0.015 82.3 - 2.425 - 91.6 0.04586 -0.262 0.00051 0.013 84.79 - 2.479 - 94.11 0.03695 -0.282 0.00048 0.015 87.28 - 2.531 - 96.6 0.02963 -0.293 0.00041 0.017 89.77 - 2.582 - 99.08 0.02384 -0.295 0.00033 0.017 92.26 - 2.631 - 101.55 0.01934 -0.317 0.00032 0.02 94.74 - 2.679 - 104.01 0.01526 -0.256 0.00028 0.023 97.23 - 2.725 - 106.45 0.01165 -0.297 0.00024 0.026 99.72 - 2.769 - 108.88 0.00979 -0.242 0.0002 0.026 102.21 - 2.813 -ENDDATA 94 -ENDSUBENT 123 -SUBENT O0395004 970707 20050926 0000 -BIB 3 18 -REACTION S(4-BE-9(P,INL)4-BE-9,PAR,DA,,,EXP) - A(4-BE-9(P,INL)4-BE-9,PAR,POL/DA,,ANA,EXP) -ERR-ANALYS (ERR-1) Upper Limit of Systematic Uncertainty of - Scattered Proton Energy For Forward Directions. - (ERR-2) Systematic Incertainty of Scattered Proton - Energy For Backward Directions. - (ERR-3) Systematic Uncertainty of Scattering Angle For - Forward Directions. - (ERR-4) Systematic Uncertainty of Scattering Angle For - Backward Directions. - (ERR-7) Solid Angle Uncertainty For Forward Directions. - (ERR-8) Solid Angle Uncertainty For Backward - Directions. - (ERR-9) Target Thickness Uncertainty For Forward - Directions. - (ERR-10) Target Thickness Uncertainty For Backward - Directions. -EN-SEC (E-LVL,4-BE-9) -ENDBIB 18 -COMMON 10 6 -EN ERR-2 ERR-3 ERR-4 ERR-7 ERR-8 -ERR-9 ERR-1 ERR-10 E-LVL -MEV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT -PER-CENT PER-CENT PER-CENT MEV - 54.7 0.5 1. 0.5 2. 1. - 3. 0.5 2. 2.429 -ENDCOMMON 6 -DATA 7 53 -ANG-CM DATA SDATA AERR-T SERR-T AMISC1 -MISC2 -ADEG MB/SR NO-DIM MB/SR NO-DIM ADEG -1/FM - 11.2 2.323 0.243 0.2546 0.137 10. - 0.286 - 13.99 2.812 -0.15 0.2632 0.123 12.5 - 0.356 - 16.79 3.863 -0.178 0.37278 0.093 15. - 0.426 - 16.79 4.052 -0.086 0.28121 0.125 15. - 0.426 - 19.58 4.944 -0.107 0.22396 0.057 17.5 - 0.496 - 22.36 5.598 -0.113 0.29781 0.07 20. - 0.565 - 25.14 6.594 -0.067 0.26376 0.05 22.5 - 0.634 - 27.92 6.771 -0.068 0.18349 0.034 25. - 0.703 - 30.69 7.331 -0.078 0.11143 0.018 27.5 - 0.771 - 33.45 6.932 -0.074 0.12547 0.022 30. - 0.838 - 36.21 6.755 -0.075 0.10876 0.019 32.5 - 0.905 - 38.96 5.886 -0.102 0.12066 0.02 34.99 - 0.971 - 38.96 6.042 -0.117 0.09909 0.021 34.99 - 0.971 - 38.96 6.23 -0.119 0.09158 0.019 34.99 - 0.971 - 38.96 6.316 -0.188 0.10485 0.027 34.99 - 0.971 - 38.96 6.475 -0.039 0.11396 0.021 34.99 - 0.971 - 38.96 6.536 -0.041 0.11373 0.021 34.99 - 0.971 - 38.96 6.562 -0.058 0.11155 0.021 34.99 - 0.971 - 38.96 6.601 -0.069 0.11288 0.021 34.99 - 0.971 - 38.96 6.604 -0.069 0.10434 0.019 34.99 - 0.971 - 38.96 6.642 -0.074 0.10295 0.02 34.99 - 0.971 - 38.96 6.657 -0.082 0.11517 0.019 34.99 - 0.971 - 38.96 6.699 -0.092 0.10919 0.018 34.99 - 0.971 - 38.96 6.716 -0.095 0.11081 0.02 34.99 - 0.971 - 38.96 6.729 -0.096 0.10699 0.02 34.99 - 0.971 - 41.7 5.443 -0.13 0.08056 0.018 37.5 - 1.036 - 44.43 4.555 -0.128 0.06331 0.017 39.99 - 1.101 - 47.16 3.693 -0.123 0.04727 0.015 42.49 - 1.164 - 49.88 2.948 -0.143 0.03449 0.013 44.99 - 1.227 - 52.58 2.255 -0.155 0.02977 0.015 47.49 - 1.289 - 55.28 1.775 -0.208 0.02361 0.016 49.99 - 1.35 - 57.97 1.391 -0.17 0.0192 0.016 52.49 - 1.41 - 60.65 1.099 -0.133 0.01528 0.017 54.99 - 1.469 - 63.31 0.8934 -0.08 0.01394 0.019 57.49 - 1.527 - 65.97 0.7234 -0.039 0.01237 0.012 59.99 - 1.584 - 65.97 0.7522 -0.045 0.00797 0.021 59.99 - 1.584 - 68.61 0.6416 0.03 0.01001 0.019 62.49 - 1.64 - 71.24 0.5502 0.099 0.0071 0.015 64.99 - 1.695 - 73.86 0.4881 0.15 0.01323 0.037 67.49 - 1.748 - 76.47 0.415 0.196 0.00697 0.022 69.99 - 1.801 - 79.07 0.3555 0.215 0.00519 0.017 72.49 - 1.852 - 81.65 0.309 0.222 0.00445 0.017 74.99 - 1.902 - 84.22 0.2489 0.272 0.00406 0.019 77.49 - 1.951 - 86.78 0.2102 0.228 0.00456 0.024 79.99 - 1.999 - 89.32 0.1707 0.261 0.00348 0.027 82.49 - 2.045 - 91.85 0.1321 0.236 0.00729 0.082 84.99 - 2.091 - 94.37 0.1102 0.244 0.00201 0.022 87.49 - 2.134 - 96.88 0.08647 0.196 0.00181 0.025 89.99 - 2.177 - 99.37 0.06887 0.225 0.00167 0.03 92.49 - 2.219 - 101.85 0.05515 0.249 0.00144 0.032 94.99 - 2.259 - 104.31 0.04218 0.234 0.00128 0.038 97.49 - 2.298 - 106.77 0.03637 0.318 0.00117 0.04 99.99 - 2.335 - 109.21 0.02921 0.316 0.00076 0.032 102.49 - 2.372 -ENDDATA 110 -ENDSUBENT 140 -SUBENT O0395005 970707 20050926 0000 -BIB 3 18 -REACTION S(4-BE-9(P,INL)4-BE-9,PAR,DA,,,EXP) - A(4-BE-9(P,INL)4-BE-9,PAR,POL/DA,,ANA,EXP) -ERR-ANALYS (ERR-1) Upper Limit of Systematic Uncertainty of - Scattered Proton Energy For Forward Directions. - (ERR-2) Systematic Incertainty of Scattered Proton - Energy For Backward Directions. - (ERR-3) Systematic Uncertainty of Scattering Angle For - Forward Directions. - (ERR-4) Systematic Uncertainty of Scattering Angle For - Backward Directions. - (ERR-7) Solid Angle Uncertainty For Forward Directions. - (ERR-8) Solid Angle Uncertainty For Backward - Directions. - (ERR-9) Target Thickness Uncertainty For Forward - Directions. - (ERR-10) Target Thickness Uncertainty For Backward - Directions. -EN-SEC (E-LVL,4-BE-9) -ENDBIB 18 -COMMON 10 6 -EN ERR-2 ERR-3 ERR-4 ERR-7 ERR-8 -ERR-9 ERR-1 ERR-10 E-LVL -MEV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT -PER-CENT PER-CENT PER-CENT MEV - 74.72 2. 1.5 0.5 2.5 1.5 - 3. 1. 1. 2.429 -ENDCOMMON 6 -DATA 7 45 -ANG-CM DATA SDATA AERR-T SERR-T AMISC1 -MISC2 -ADEG MB/SR NO-DIM MB/SR NO-DIM ADEG -1/FM - 11.21 2.044 -0.079 0.23935 0.153 10. - 0.336 - 14.01 2.546 -0.077 0.40049 0.199 12.5 - 0.419 - 16.81 3.599 0.009 0.26273 0.094 15. - 0.502 - 19.6 5.104 0.038 0.2501 0.064 17.5 - 0.584 - 22.38 5.623 0.067 0.25191 0.058 20. - 0.666 - 25.17 6.418 0.03 0.21629 0.043 22.5 - 0.747 - 27.95 6.455 0.048 0.18203 0.035 25. - 0.828 - 27.95 6.565 0.074 0.17857 0.035 25. - 0.828 - 30.72 5.801 0.09 0.14851 0.032 27.5 - 0.908 - 33.49 5.687 0.062 0.16435 0.038 30. - 0.987 - 36.25 4.801 0.053 0.06769 0.017 32.5 - 1.066 - 39. 3.932 0.05 0.05112 0.016 35. - 1.144 - 41.74 3.089 0.041 0.04016 0.016 37.49 - 1.221 - 44.48 2.385 0.019 0.02862 0.014 39.99 - 1.297 - 47.21 1.781 -0.034 0.02333 0.016 42.49 - 1.372 - 49.93 1.35 -0.057 0.01823 0.016 44.99 - 1.446 - 49.93 1.389 -0.062 0.02764 0.025 44.99 - 1.446 - 49.93 1.4 -0.085 0.0196 0.017 44.99 - 1.446 - 52.64 1.066 -0.086 0.01567 0.018 47.49 - 1.519 - 55.34 0.8329 -0.103 0.01349 0.02 49.99 - 1.591 - 55.34 0.8515 -0.121 0.01073 0.015 49.99 - 1.591 - 58.03 0.6911 -0.106 0.00892 0.015 52.49 - 1.661 - 60.7 0.5839 -0.131 0.00823 0.017 54.99 - 1.731 - 63.37 0.4941 -0.116 0.00687 0.017 57.49 - 1.799 - 66.03 0.4181 -0.109 0.00623 0.018 59.99 - 1.866 - 68.54 0.3507 -0.112 0.00382 0.013 62.36 - 1.929 - 68.54 0.3592 -0.077 0.00352 0.011 62.36 - 1.929 - 68.54 0.3796 -0.093 0.00361 0.01 62.36 - 1.929 - 68.67 0.3454 -0.073 0.00511 0.018 62.49 - 1.932 - 71.16 0.2754 -0.065 0.00306 0.013 64.85 - 1.993 - 73.78 0.2275 -0.064 0.00234 0.012 67.35 - 2.056 - 76.38 0.1733 -0.093 0.00194 0.013 69.84 - 2.118 - 78.96 0.1301 -0.07 0.00137 0.012 72.33 - 2.178 - 81.54 0.0925 -0.08 0.00095 0.012 74.82 - 2.237 - 84.1 0.06533 -0.097 0.00082 0.015 77.31 - 2.294 - 86.65 0.04952 -0.114 0.00067 0.016 79.8 - 2.35 - 89.19 0.03341 -0.126 0.00054 0.02 82.29 - 2.405 - 91.71 0.02442 -0.124 0.00055 0.029 84.78 - 2.458 - 94.22 0.01734 -0.024 0.00037 0.027 87.27 - 2.51 - 96.71 0.01223 -0.081 0.00028 0.03 89.76 - 2.56 - 99.2 0.01042 0.018 0.00025 0.031 92.25 - 2.608 - 101.66 0.00764 0.109 0.00118 0.218 94.74 - 2.656 - 104.12 0.00789 0.054 0.00051 0.087 97.23 - 2.701 - 106.56 0.00674 0.092 0.00026 0.051 99.71 - 2.745 - 108.98 0.00547 0.228 0.00027 0.07 102.2 - 2.788 -ENDDATA 94 -ENDSUBENT 124 +HISTORY (19970701C) + (20110711D) Duplication of EXFOR E1581 +ENDBIB 16 +NOCOMMON 0 0 +ENDSUBENT 19 +NOSUBENT O0395002 20110711 20111003 20110913 O045 +NOSUBENT O0395003 20110711 20111003 20110913 O045 +NOSUBENT O0395004 20110711 20111003 20110913 O045 +NOSUBENT O0395005 20110711 20111003 20110913 O045 ENDENTRY 5 diff --git a/exforall/O04/O0443.x4 b/exforall/O04/O0443.x4 index cc1bfd908..ebd384468 100644 --- a/exforall/O04/O0443.x4 +++ b/exforall/O04/O0443.x4 @@ -1,48 +1,51 @@ -ENTRY O0443 20010208 20030424 20050926 0000 -SUBENT O0443001 20010208 20030424 20050926 0000 -BIB 12 31 +ENTRY O0443 20110322 20111003 20110913 O045 +SUBENT O0443001 20110322 20111003 20110913 O045 +BIB 12 36 TITLE Elastic and Inelastic Scattering of 14.1-MeV Protons by Medium Weight Nuclei. -AUTHOR (K.KIKUCHI,S.KOBAYASHI,K.MATSUDA) +AUTHOR (K.Kikuchi,S.Kobayashi,K.Matsuda) INSTITUTE (2JPNTOK) REFERENCE (J,JPJ,14,121,1959) -HISTORY (19980708C) - (20010208A) Correction According to McLane's Remarks - From 20010206. - (20010208U) Last checking has been done. -SAMPLE The Target Foils were Obtained from Commercial Sources, - Except Cr Foils. - Rolled Foils of Iron and Titanium were About 5 Mum - Thick. - The Cr Foils were Prepared by Electroplating and had a - Contamination of Oxygen. - The Thickness of the Nickel Foils was About 1 Mg/Cm**2 - And the Chromium Foil was About 0.5 Mg/Cm**2. -ADD-RES (COMP).Born Approximation. -DETECTOR (NAICR). A NaI(Tl) Crystal of Dimension of About +SAMPLE The target foils were obtained from commercial sources, + except Cr foils. + Rolled foils of Iron and Titanium were about 5 mu-m + thick. + The Cr foils were prepared by electroplating and had a + contamination of Oxygen. + The thickness of the Nickel foils was about 1 mg/cm**2 + and the Chromium foil was about 0.5 mg/cm**2. +ADD-RES (COMP).Born approximation. +DETECTOR (NAICR). A NaI(Tl) crystal of dimension of about 18*18*1.4 mm. FACILITY (CYCLO,2JPNTOK).The I.N.S.(TOKYO) Cyclotron. METHOD (SITA,BCINT) -ERR-ANALYS The Errors of the Differential Cross Sections of - Elastic Scattering were not More Than 5%, Which was - Mainly Due to the Inaccuracy of the Integrator, the - Non-Uniformity of Target Foils and Some Effects of the - Slit Edge Scattering. - Most Errors of the Inelastic Cross Section Come from - The Back-Ground Subtraction Especially in Forward - Angles. +ERR-ANALYS The errors of the differential cross sections of + elastic scattering were not more than 5%, which was + mainly due to the inaccuracy of the integrator, the + non-uniformity of target foils and some effects of the + slit edge scattering + Most errors of the inelastic cross section come from + the back-ground subtraction especially in forward + angles. + (ANG-ERR-D) Digitizing error + (ERR-DIG) Digitizing error STATUS (CURVE).By CAJAD. -ENDBIB 31 -NOCOMMON -ENDSUBENT 34 -SUBENT O0443002 20010208 20030424 20050926 0000 -BIB 2 3 +HISTORY (19980708C) + (20010208A) Correction according to McLane's remarks + From 20010206. + (20010208U) Last checking has been done. + (20110322A) SD: In all Subents ANG-ERR =. ANG-ERR-D; + DATA-ERR => ERR-DIG (where it is relevant). + Both moved to BIB section of Subent 001 +ENDBIB 36 +NOCOMMON 0 0 +ENDSUBENT 39 +SUBENT O0443002 20110322 20111003 20110913 O045 +BIB 1 1 REACTION (28-NI-0(P,EL)28-NI-0,,DA) Figure 4. -ERR-ANALYS (DATA-ERR).Data-Point Reader Uncertainty. - (ANG-ERR).Data-Point Reader Uncertainty. -ENDBIB 3 +ENDBIB 1 COMMON 3 3 -EN ANG-ERR DATA-ERR +EN ANG-ERR-D ERR-DIG MEV ADEG PER-CENT 14.1 0.9 3. ENDCOMMON 3 @@ -81,15 +84,15 @@ ADEG MB/SR 169.4 10.6 176.2 11.7 ENDDATA 33 -ENDSUBENT 45 -SUBENT O0443003 20010208 20030424 20050926 0000 +ENDSUBENT 43 +SUBENT O0443003 20110322 20111003 20110913 O045 BIB 2 3 REACTION (26-FE-0(P,EL)26-FE-0,,DA) Figure 5 ERR-ANALYS (DATA-ERR).Data-Point Reader Uncertainty. (ANG-ERR).Data-Point Reader Uncertainty. ENDBIB 3 COMMON 2 3 -ANG-ERR DATA-ERR +ANG-ERR-D ERR-DIG ADEG PER-CENT 0.9 4. ENDCOMMON 3 @@ -147,14 +150,12 @@ MEV ADEG MB/SR 14.1 166.9 8.8 ENDDATA 51 ENDSUBENT 63 -SUBENT O0443004 20010208 20030424 20050926 0000 -BIB 2 3 +SUBENT O0443004 20110322 20111003 20110913 O045 +BIB 1 1 REACTION (24-CR-0(P,EL)24-CR-0,,DA) Figure 6. -ERR-ANALYS (DATA-ERR).Data-Point Reader Uncertainty. - (ANG-ERR).Data-Point Reader Uncertainty. -ENDBIB 3 +ENDBIB 1 COMMON 3 3 -EN ANG-ERR DATA-ERR +EN ANG-ERR-D ERR-DIG MEV ADEG PER-CENT 14.1 0.8 3. ENDCOMMON 3 @@ -194,15 +195,13 @@ ADEG MB/SR 160.2 6.75 165.7 7.1 ENDDATA 34 -ENDSUBENT 46 -SUBENT O0443005 20010208 20030424 20050926 0000 -BIB 2 3 +ENDSUBENT 44 +SUBENT O0443005 20110322 20111003 20110913 O045 +BIB 1 1 REACTION (22-TI-0(P,EL)22-TI-0,,DA) Figure 7. -ERR-ANALYS (DATA-ERR).Data-Point Reader Uncertainty. - (ANG-ERR).Data-Point Reader Uncertainty. -ENDBIB 3 +ENDBIB 1 COMMON 3 3 -EN ANG-ERR DATA-ERR +EN ANG-ERR-D ERR-DIG MEV ADEG PER-CENT 14.1 0.8 4. ENDCOMMON 3 @@ -228,34 +227,32 @@ ADEG MB/SR 151. 3.57 161.5 5.45 ENDDATA 20 -ENDSUBENT 32 -SUBENT O0443006 20010208 20030424 20050926 0000 -BIB 4 10 +ENDSUBENT 30 +SUBENT O0443006 20110322 20111003 20110913 O045 +BIB 4 8 REACTION (28-NI-0(P,INL)28-NI-0,PAR,DA) Figure 8 -EN-SEC (E-LVL,28-NI-58) +EN-SEC (E-EXC,28-NI-58) Ni-58 (67.76%) Has First Excited State at 1.45 MeV Ni-60 (26.16%) Has First Excited State at 1.33 MeV Ni-61 (1.16%) Has First Excited State at 1.34 MeV. -LEVEL-PROP (28-NI-58,E-LVL=1.45,SPIN=2.,PARITY=+1.) - (28-NI-60,E-LVL=1.33,SPIN=2.,PARITY=+1.) - (28-NI-61,E-LVL=1.34) -ERR-ANALYS (ERR-T).The Uncertainty is Reported by Authors. - (ANG-ERR).Data-Point Reader Uncertainty. -ENDBIB 10 -COMMON 3 3 -EN E-LVL ANG-ERR -MEV MEV ADEG - 14.1 1.4 0.8 +ERR-ANALYS (DATA-ERR).The Uncertainty is Reported by Authors. +HISTORY (20110322A) SD: Title E-LVL changed on E-EXC. + LEVEL-PROP deleted. +ENDBIB 8 +COMMON 4 3 +EN E-EXC ANG-ERR-D ERR-DIG +MEV MEV ADEG MB/SR + 14.1 1.4 0.8 0.01 ENDCOMMON 3 DATA 3 31 -ANG-CM DATA-CM ERR-T +ANG-CM DATA-CM DATA-ERR ADEG MB/SR MB/SR 25.9 7.8 3. 28.5 9.6 3. 29.7 9.7 1.3 32.5 10.2 1. 34.9 9.8 1. - 37.7 11. 0.7 + 37.7 11.0 0.7 40.3 9.8 0.6 43.7 10.2 0.5 47. 8.5 0.9 @@ -282,24 +279,23 @@ ADEG MB/SR MB/SR 161.4 1.55 0.13 164.9 1.62 0.14 ENDDATA 33 -ENDSUBENT 52 -SUBENT O0443007 20010208 20030424 20050926 0000 -BIB 4 7 +ENDSUBENT 50 +SUBENT O0443007 20110322 20111003 20110913 O045 +BIB 4 6 REACTION ((26-FE-0(P,INL)26-FE-0,PAR,DA)= (26-FE-56(P,INL)26-FE-56,PAR,DA,,A)) .Figure 9. Only Fe-56 (91.68%) Has Excited State at 0.845 MeV EN-SEC (E-LVL,26-FE-56) LEVEL-PROP (26-FE-56,E-LVL=0.845,SPIN=2.,PARITY=+1.) -ERR-ANALYS (ERR-T).The Uncertainty is Reported by Authors. - (ANG-ERR).Data-Point Reader Uncertainty. -ENDBIB 7 -COMMON 3 3 -EN E-LVL ANG-ERR -MEV MEV ADEG - 14.1 0.845 0.8 +ERR-ANALYS (DATA-ERR).The Uncertainty is Reported by Authors. +ENDBIB 6 +COMMON 4 3 +EN E-LVL ANG-ERR-D ERR-DIG +MEV MEV ADEG MB/SR + 14.1 0.845 0.8 0.01 ENDCOMMON 3 DATA 3 22 -ANG-CM DATA-CM ERR-T +ANG-CM DATA-CM DATA-ERR ADEG MB/SR MB/SR 27.2 11.3 1.6 28.9 12.4 1.4 @@ -324,73 +320,73 @@ ADEG MB/SR MB/SR 150.1 1.18 0.23 160.2 1.1 0.19 ENDDATA 24 -ENDSUBENT 40 -SUBENT O0443008 20010208 20030424 20050926 0000 -BIB 4 7 +ENDSUBENT 39 +SUBENT O0443008 20110322 20111003 20110913 O045 +BIB 5 7 REACTION ((24-CR-0(P,INL)24-CR-0,PAR,DA)= (24-CR-52(P,INL)24-CR-52,PAR,DA,,A)) .Figure 10. - Only Cr-52 (83.76%) Has Excited State at 1.45 MeV. + Only Cr-52 (83.76%) has excited state at 1.45 MeV. EN-SEC (E-LVL,24-CR-52) LEVEL-PROP (24-CR-52,E-LVL=1.45,SPIN=2.,PARITY=+1.) -ERR-ANALYS (ERR-T).The Uncertainty is Reported by Authors. - (ANG-ERR).Data-Point Reader Uncertainty. +ERR-ANALYS (DATA-ERR).The Uncertainty is reported by authors. +HISTORY (20110322A) SD: Data were redigitized. ENDBIB 7 -COMMON 3 3 -EN E-LVL ANG-ERR -MEV MEV ADEG - 14.1 1.45 0.8 +COMMON 4 3 +EN E-LVL ANG-ERR-D ERR-DIG +MEV MEV ADEG MB/SR + 14.1 1.45 0.5 0.0045 ENDCOMMON 3 DATA 3 30 -ANG-CM DATA-CM ERR-T +ANG-CM DATA-CM DATA-ERR ADEG MB/SR MB/SR - 51.6 2.6 0.7 - 52.6 1.9 0.5 - 56.9 2.8 0.4 - 60.5 3. 0.4 - 63.9 2.9 0.6 - 65.8 3.37 0.3 - 70.1 3.9 0.3 - 75.2 3.57 0.29 - 80.8 2.97 0.18 - 85.7 2.31 0.16 - 89.6 1.73 0.15 - 95.4 1.57 0.15 - 99.9 1.28 0.15 - 106.2 1.19 0.12 - 110.2 1.04 0.12 - 121.3 1.26 0.13 - 126.1 1.48 0.12 - 131.3 1.39 0.13 - 136.5 1.45 0.13 - 145.7 1.31 0.14 - 150.3 1.15 0.13 - 156.6 0.86 0.12 - 161.8 0.91 0.12 - 165.8 0.68 0.15 - 171.1 0.85 0.12 - 176.3 0.91 0.12 - 181.5 0.65 0.12 - 185.5 0.63 0.13 - 190.8 0.81 0.13 - 195.9 0.59 0.12 + 21.9 2.5719 0.6897 + 24.4 1.9640 0.4773 + 27.0 2.7775 0.3855 + 30.6 2.9697 0.3593 + 33.8 2.8419 0.5849 + 35.1 3.3798 0.3120 + 40.2 3.8871 0.3146 + 45.6 3.5656 0.2885 + 50.5 2.9661 0.1810 + 55.3 2.2905 0.1599 + 60.3 1.7356 0.1705 + 65.4 1.5714 0.1548 + 70.1 1.2787 0.1600 + 75.5 1.1855 0.1259 + 80.3 1.0317 0.1417 + 90.4 1.2516 0.1181 + 95.8 1.4809 0.1260 + 100.5 1.3927 0.1575 + 105.5 1.4489 0.1365 + 115.8 1.2963 0.1547 + 121.0 1.1453 0.1469 + 126.1 0.8527 0.1364 + 131.3 0.9168 0.1311 + 136.4 0.6713 0.1810 + 141.0 0.8454 0.1233 + 146.2 0.9095 0.1285 + 151.7 0.6353 0.1391 + 156.5 0.6284 0.1443 + 161.6 0.7973 0.1337 + 166.5 0.5755 0.1337 ENDDATA 32 ENDSUBENT 48 -SUBENT O0443009 20010208 20030424 20050926 0000 +SUBENT O0443009 20110322 20111003 20110913 O045 BIB 4 6 REACTION (22-TI-0(P,INL)22-TI-0,PAR,DA) Figure 11. -EN-SEC (E-LVL,22-TI-48) -LEVEL-PROP (22-TI-48,E-LVL=0.99,SPIN=2.,PARITY=+1.) 78.45% - (22-TI-46,E-LVL=0.89,SPIN=2.,PARITY=+1.) 7.95% -ERR-ANALYS (ERR-T).The Uncertainty is Reported by Authors. - (ANG-ERR).Data-Point Reader Uncertainty. +EN-SEC (E-EXC,22-TI-48) +ERR-ANALYS (DATA-ERR).The Uncertainty is reported by authors. +HISTORY (20110322A) SD: Title E-LVL changed on E-EXC, value + changed according to the text of the article. + LEVEL-PROP deleted. ENDBIB 6 -COMMON 3 3 -EN E-LVL ANG-ERR -MEV MEV ADEG - 14.1 0.99 0.8 +COMMON 4 3 +EN E-EXC ANG-ERR-D ERR-DIG +MEV MEV ADEG MB/SR + 14.1 1.0 0.8 0.01 ENDCOMMON 3 DATA 3 17 -ANG-CM DATA-CM ERR-T +ANG-CM DATA-CM DATA-ERR ADEG MB/SR MB/SR 23. 6.6 1.3 30. 6.4 1.1 diff --git a/exforall/O05/O0501.x4 b/exforall/O05/O0501.x4 index 2af359985..5eb970df6 100644 --- a/exforall/O05/O0501.x4 +++ b/exforall/O05/O0501.x4 @@ -1,61 +1,60 @@ -ENTRY O0501 19991117 20030923 20050926 0000 -SUBENT O0501001 19991117 20030923 20050926 0000 -BIB 13 47 +ENTRY O0501 20110313 20111003 20110913 O045 +SUBENT O0501001 20110313 20111003 20110913 O045 +BIB 13 50 TITLE Production of Be-7, Na-22 and Mg-28 from Mg, Al and - SiO(2) Protons Between 82 and 800 MeV. -AUTHOR (H.R.HEYDEGGER,A.L.TURKEVICH,A.VAN GINNEKEN, - P.H.WALPOLE) + SiO(2) protons between 82 and 800 MeV. +AUTHOR (H.R.Heydegger,A.L.Turkevich,A.Van Ginneken, + P.H.Walpole) INSTITUTE (1USAPUR).Purdue University, Hammond, Indiana. (1USACHI).The University of Chicago, Enrico Fermi Institute. (1USANAL) REFERENCE (J,PR/C,14,1506,1976) -HISTORY (19990120C) - (19990511U) Last checking has been done. - (19991117A) DATE is corrected -SAMPLE The Individual Targets Utilized were: - 1. 19.9-22.5 mg/cm**2 Mg Purity >99.8%. - Admixtures: Na <50 Ppm, Al < Ppm, (SI) Less 50 Ppm), - 2. 5.29-7.27 mg/cm**2 Al Purity >99.9%, - Admixtures: Na+Mg < 500 Ppm, Si < 500 Ppm. - 3. 209-237 mg/cm**2 Sio(2) Purity >99.9999%. - Admixtures: Boron < 0.01 Ppm, Na <0.1 Ppm, Mg <0.1 - Ppm, Al < 0.1 Ppm. - The Mg and SiO(2) Targets were Irradiated Individually, - The Al Targets were Nearly All Run As Portions of - Target Stacks Involving from 45 to 1000 mg/cm**2 of - Other (MUCH HIGHER Z) Materials. -ADD-RES (COMP).Empirical Formulas and Monte Carlo Method. -DETECTOR (NAICR).Some Early Radioactivity Measurements (ALL ON - ALUMINUM RUNS) Were Made with a 7.6 cm*7.6 cm NaI(Tl) - Multichannel Analyzer System. - (GELI).Two Different 42 cm**3 Ge(Li). Multichannel - Analyzer System. +SAMPLE The individual targets utilized were: + 1. 19.9-22.5 mg/cm**2 Mg purity >99.8%. + admixtures: Na <50 ppm, Al < ppm, (SI) Less 50 ppm), + 2. 5.29-7.27 mg/cm**2 Al purity >99.9%, + admixtures: Na+Mg < 500 ppm, Si < 500 ppm. + 3. 209-237 mg/cm**2 SiO(2) purity >99.9999%. + admixtures: Boron < 0.01 ppm, Na <0.1 ppm, Mg <0.1 + ppm, Al < 0.1 ppm. + The Mg and SiO(2) targets were irradiated individually, + The Al targets were nearly all run as portions of + target stacks involving from 45 to 1000 mg/cm**2 of + other (much higher Z) materials. +ADD-RES (COMP).Empirical formulas and Monte Carlo method. +DETECTOR (NAICR).Some early radioactivity measurements (all on + aluminum runs) were made with a 7.6 cm*7.6 cm NaI(Tl) + multichannel analyzer system. + (GELI).Two different 42 cm**3 Ge(Li). Multichannel + analyzer system. FACILITY (SYNCY,1USACHI) (MESON,1USALAS) 800 and 400 MeV. METHOD (BCINT) - (ACTIV) Irradiation Durations Ranged from Five Minutes - To One Hour with Typical Integrated Proton Intensities - Of the 10.E16. + (ACTIV) Irradiation durations ranged from five minutes + to one hour with typical integrated proton intensities + of the 10.**16. (STTA) - (INTB) Proton Beam of University of Chicago - Synchrocyclotron. + (INTB) Proton beam of University of Chicago + Synchrocyclotron. (EXTB) At the Los Alamos. DECAY-MON (11-NA-24,0.625D,DG,1369.,1.) -ERR-ANALYS (ERR-1) Standard Deviations are Estimated to be 10% For - Na-22 and Be-7 from All Targets,Including Monitor Cross - Section Precision. - (ERR-2) And 15% For Mg-28. +ERR-ANALYS (DATA-ERR) Standard deviations are estimated to be 10% + for Na-22 and Be-7 from all targets,including monitor + cross section precision and 15% for Mg-28. (EN-ERR).The Uncertainty is Reported by Authors. STATUS (TABLE) -ENDBIB 47 -COMMON 2 3 -ERR-1 ERR-2 -PER-CENT PER-CENT - 10. 15. -ENDCOMMON 3 -ENDSUBENT 54 -SUBENT O0501002 19991117 20030923 20050926 0000 +HISTORY (19990120C) + (19990511U) Last checking has been done. + (19991117A) DATE is corrected + (20110313A) SD: In Subent 003.3 value 10.1 mb + (at 111 MeV) from DATA 3 moved to MONIT + COMMON moved to Subents 002-004. + ERR-1 and ERR-2 => DATA-ERR +ENDBIB 50 +NOCOMMON 0 0 +ENDSUBENT 53 +SUBENT O0501002 20110313 20111003 20110913 O045 BIB 5 10 REACTION 1(12-MG-0(P,X)11-NA-22,CUM,SIG) 2(12-MG-0(P,X)4-BE-7,IND,SIG) @@ -64,11 +63,15 @@ RAD-DET 2(4-BE-7,DG) DECAY-DATA1(11-NA-22,949.D,DG,1275.) 2(4-BE-7,53.D,DG,478.,0.103) MONITOR ((MONIT)12-MG-0(P,X)11-NA-24,,SIG) -MONIT-REF (C0252001,R.G.KORTELING+,J,PR/C,1,193,1970).At 400 MeV. - (C0253001,R.G.KORTELING+,J,PR/C,1,1960,1970) - (O0412001,R.G.KORTELING+,J,JIN,29,2863,1967) +MONIT-REF (C0252001,R.G.Korteling+,J,PR/C,1,193,1970).At 400 MeV. + (C0253001,R.G.Korteling+,J,PR/C,1,1960,1970) + (O0412001,R.G.Korteling+,J,JIN,29,2863,1967) ENDBIB 10 -NOCOMMON +COMMON 1 3 +DATA-ERR +PER-CENT + 10. +ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA 1DATA 2MONIT MEV MEV MB MB MB @@ -77,9 +80,9 @@ MEV MEV MB MB MB 290. 17. 32. 2.9 4.8 435. 24. 31. 4. 5.2 ENDDATA 6 -ENDSUBENT 21 -SUBENT O0501003 19991117 20030923 20050926 0000 -BIB 6 16 +ENDSUBENT 25 +SUBENT O0501003 20110313 20111003 20110913 O045 +BIB 7 18 REACTION 1(13-AL-27(P,X)11-NA-22,CUM,SIG) 2(13-AL-27(P,X)12-MG-28,CUM,SIG) 3(13-AL-27(P,X)4-BE-7,IND,SIG) @@ -95,14 +98,20 @@ DECAY-DATA1(11-NA-22,949.D,DG,1275.) (13-AL-28,0.0016D,DG,1780.,1.) 3(4-BE-7,53.D,DG,478.,0.103) MONITOR ((MONIT)13-AL-27(P,X)11-NA-24,CUM,SIG) -MONIT-REF (B0022001,J.B.CUMMING,J,ARN,13,261,1963) -ENDBIB 16 -NOCOMMON +MONIT-REF (B0022001,J.B.Cumming,J,ARN,13,261,1963) +HISTORY (20110313A) SD: value 10.1 mb(at 111 MeV) from DATA 3 + moved to MONIT +ENDBIB 18 +COMMON 3 3 +DATA-ERR 1DATA-ERR 2DATA-ERR 3 +PER-CENT PER-CENT PER-CENT + 10. 15. 10. +ENDCOMMON 3 DATA 6 11 EN EN-ERR DATA 1DATA-MAX 2DATA 3MONIT MEV MEV MB MB MB MB 82. 8. 18.3 10. - 111. 10. 17.4 10.1 + 111. 10. 17.4 10.1 118. 10. 17.4 0.0002 0.8 10.1 187. 13. 14.7 9.3 218. 14. 13.5 0.0003 1.3 9.5 @@ -113,8 +122,8 @@ MEV MEV MB MB MB MB 434. 24. 14.1 0.0004 2.5 10.6 800. 5. 15. 0.02 6.4 10.5 ENDDATA 13 -ENDSUBENT 34 -SUBENT O0501004 19991117 20030923 20050926 0000 +ENDSUBENT 40 +SUBENT O0501004 20110313 20111003 20110913 O045 BIB 6 22 REACTION 1(14-SI-OXI(P,X)11-NA-22,CUM,SIG) 2(14-SI-OXI(P,X)12-MG-28,CUM,SIG) @@ -132,14 +141,18 @@ COMMENT /by Authors/.For the Sio(2) Targets,the Cross Sections Are For the Production from Si-30. Be-7 is Produced Both from O and Si in an Sio(2) Target.The Cross Section Listed is Based on - 3 Amoms/Mol. + 3 Atoms/Mol. MONITOR ((MONIT)14-SI-0(P,X)11-NA-24,CUM,SIG) -MONIT-REF (C0253001,R.G.KORTELING+,J,PR/C,1,1960,1970).Except For +MONIT-REF (C0253001,R.G.Korteling+,J,PR/C,1,1960,1970).Except for Si at 295 MeV. - (O0412001,R.G.KORTELING+,J,JIN,29,2863,1967).Except For + (O0412001,R.G.Korteling+,J,JIN,29,2863,1967).Except for Si at 295 MeV. ENDBIB 22 -NOCOMMON +COMMON 3 3 +DATA-ERR 1DATA-ERR 2DATA-ERR 3 +PER-CENT PER-CENT PER-CENT + 10. 15. 10. +ENDCOMMON 3 DATA 6 4 EN EN-ERR DATA 1DATA 2DATA 3MONIT MEV MEV MB MB MB MB @@ -148,5 +161,5 @@ MEV MEV MB MB MB MB 295. 17. 16.6 1.29 17. 3.6 435. 24. 18.4 1.58 23. 4.2 ENDDATA 6 -ENDSUBENT 33 +ENDSUBENT 37 ENDENTRY 4 diff --git a/exforall/O07/O0720.x4 b/exforall/O07/O0720.x4 index 585e9fb7d..976da4d37 100644 --- a/exforall/O07/O0720.x4 +++ b/exforall/O07/O0720.x4 @@ -1,39 +1,44 @@ -ENTRY O0720 20000427 20030923 20050926 0000 -SUBENT O0720001 20000427 20030923 20050926 0000 -BIB 10 14 +ENTRY O0720 20110313 20111003 20110913 O045 +SUBENT O0720001 20110313 20111003 20110913 O045 +BIB 10 18 TITLE Fission of Uranium by High Energy from 140 to 660-MeV Protons. -AUTHOR (N.S.IVANOVA) +AUTHOR (N.S.Ivanova) INSTITUTE (4RUSRI ) REFERENCE (J,ZET,31,413,1956) -HISTORY (20000306C) - (20000313U) Last checking has been done. - (20000427A) DATE is corrected + (J,DOK,103,573,1955) preliminary results at 460 MeV SAMPLE Uranium-238 was included in emulsion by transfusing of Uranium salt. DETECTOR (PLATE).Nuclear Emulsions of Different Type. FACILITY (SYNCY,4ZZZDUB) METHOD (SITA) STATUS (TABLE) -ENDBIB 14 -NOCOMMON -ENDSUBENT 17 -SUBENT O0720002 20000427 20030923 20050926 0000 -BIB 5 9 +HISTORY (20000306C) + (20000313U) Last checking has been done. + (20000427A) DATE is corrected + (20110313A) SD: Unit in Subent 002 corrected: mb=>barn + REL-REF on DOK,103,573,1955 moved from Subent 002 + to REFERENCE in Subent 001. +ENDBIB 18 +NOCOMMON 0 0 +ENDSUBENT 21 +SUBENT O0720002 20110313 20111003 20110913 O045 +BIB 5 10 REACTION (92-U-238(P,F),,SIG) PART-DET (FF) FLAG (1.).Nuclear Plate of G-5 Type. (2.).Nuclear Plate of P-9 Type. - (3.).Nuclear Plate of Nikfi-R Type. - (4.).Nuclear Plate of G-5 Type.It is Data from - Another Paper. Work.See Rel-Ref. -REL-REF (R,,N.S.IVANOVA+,J,DOK,103,573,1955) -ERR-ANALYS (ERR-T).The Uncertainty is Reported by Authors. -ENDBIB 9 -NOCOMMON + (3.).Nuclear Plate of NIKFI-R Type. + (4.).Nuclear Plate of G-5 Type. Final value after + analysis was taken from prev.publ.DOK,103,573,1955 +ERR-ANALYS (DATA-ERR).The uncertainty is reported by authors. +HISTORY (20110313A) SD: Units corrected: mb=>barn + REL-REF moved to REF. in Subent 001 +ENDBIB 10 +NOCOMMON 0 0 DATA 4 7 EN DATA ERR-T FLAG -MEV MB MB NO-DIM +MEV B B NO-DIM 140. 1.56 0.4 1. 140. 1.69 0.2 2. 350. 1.4 0.3 2. @@ -42,5 +47,5 @@ MEV MB MB NO-DIM 660. 0.97 0.25 3. 660. 1.01 0.3 3. ENDDATA 9 -ENDSUBENT 23 +ENDSUBENT 24 ENDENTRY 2 diff --git a/exforall/O07/O0789.x4 b/exforall/O07/O0789.x4 index b3869513d..0d42eb5a2 100644 --- a/exforall/O07/O0789.x4 +++ b/exforall/O07/O0789.x4 @@ -1,110 +1,24 @@ -ENTRY O0789 20010323 20040407 20050926 0000 -SUBENT O0789001 20010323 20040407 20050926 0000 -BIB 12 40 +ENTRY O0789 20110711 20111003 20110913 O045 +SUBENT O0789001 20110711 20111003 20110913 O045 +BIB 6 14 TITLE A Study of 0-Degree Transverse Polarization Transfer In (P,N) Reactions from C-12,C-13 and Ca-40 at 80 and 50-MeV. AUTHOR (H.SAKAI, H.OKAMURA, N.MATSUOKA, A.SHIMIZU, T.SUDA, M.IEIRI, H.M.SHIMIZU) +REFERENCE (J,NP/A,579,45,1994) +FACILITY (CYCLO,2JPNOSA) AVF Cyclotron. INSTITUTE (2JPNTOK) (2JPNOSA) (2JPNTOH) (2JPNTSU) -REFERENCE (J,NP/A,579,45,1994) HISTORY (20001031C) - (20001228U) Last checking has been done. (20010323A) DATE is corrected -SAMPLE The Targets were Self-Supporting Plates with Thickness - Of 25-40 Mg/Cm**2. -INC-SPECT *En-Rsl* the Overall Energy Resolution Obtained - Depended Upon the Particular Targets and Flight Path - Used But were Generally in the Range of - 1.2IPA) +ENDBIB 5 +COMMON 3 3 +ERR-DIG ANG-MIN ANG-MAX +MB ADEG ADEG +0.14 0.6 1.1 ENDCOMMON 3 DATA 3 18 EN ELEMENT DATA @@ -617,18 +586,19 @@ MEV/A NO-DIM MB 300. 13. 4.61 300. 14. 3.41 ENDDATA 20 -ENDSUBENT 33 -SUBENT O1658015 20081117 20081219 20081219 O037 -BIB 3 4 -REACTION (1-H-2(14-SI-28,X)ELEM,,SIG) fig 5 +ENDSUBENT 34 +SUBENT O1658015 20110313 20111003 20110913 O045 +BIB 4 5 +REACTION (1-H-2(14-SI-28,X)ELEM,,IPA) fig 5 ERR-ANALYS (ERR-DIG).Digitizing error of data. ANALYSIS The cross section for recoils of different charge detected by SAD. -ENDBIB 4 -COMMON 1 3 -ERR-DIG -MB -0.20 +HISTORY (20110313A) SD: SF6 in REACTION code changed (SIG->IPA) +ENDBIB 5 +COMMON 3 3 +ERR-DIG ANG-MIN ANG-MAX +MB ADEG ADEG +0.20 0.6 1.1 ENDCOMMON 3 DATA 3 16 EN ELEMENT DATA @@ -650,14 +620,16 @@ MEV/A NO-DIM MB 300. 13. 6.87 300. 14. 4.72 ENDDATA 18 -ENDSUBENT 31 -SUBENT O1658016 20081117 20081219 20081219 O037 -BIB 3 4 -REACTION (1-H-1(14-SI-28,X)ELEM,,SIG) fig 6 +ENDSUBENT 32 +SUBENT O1658016 20110313 20111003 20110913 O045 +BIB 4 6 +REACTION (1-H-1(14-SI-28,X)ELEM,,SIG,,MSC) fig 6 + integrated near 0 deg ERR-ANALYS (ERR-DIG).Digitizing error of data. ANALYSIS The cross section for recoils of different charge detected by ZAD. -ENDBIB 4 +HISTORY (20110313A) SD: SF8=MSC in REACTION code added. +ENDBIB 6 COMMON 1 3 ERR-DIG PER-CENT @@ -685,14 +657,16 @@ MEV/A NO-DIM MB 300. 13. 1.82 300. 14. 5.00 ENDDATA 20 -ENDSUBENT 33 -SUBENT O1658017 20081117 20081219 20081219 O037 -BIB 3 4 -REACTION (1-H-2(14-SI-28,X)ELEM,,SIG) fig 6 +ENDSUBENT 35 +SUBENT O1658017 20110313 20111003 20110913 O045 +BIB 4 6 +REACTION (1-H-2(14-SI-28,X)ELEM,,SIG,,MSC) fig 6 + integrated near 0 deg ERR-ANALYS (ERR-DIG).Digitizing error of data. ANALYSIS The cross section for recoils of different charge detected by ZAD. -ENDBIB 4 +HISTORY (20110313A) SD: SF8=MSC in REACTION code added. +ENDBIB 6 COMMON 1 3 ERR-DIG PER-CENT @@ -720,15 +694,17 @@ MEV/A NO-DIM MB 300. 13. 2.45 300. 14. 8.40 ENDDATA 20 -ENDSUBENT 33 -SUBENT O1658018 20081117 20081219 20081219 O037 -BIB 3 5 -REACTION (1-H-1(14-SI-28,X)ELEM,,SIG) fig 9 +ENDSUBENT 35 +SUBENT O1658018 20110313 20111003 20110913 O045 +BIB 4 7 +REACTION (1-H-1(14-SI-28,X)ELEM,,SIG,,MSC) fig 9 + in coincidence with He in ang=3.9-11.7 deg ERR-ANALYS (ERR-DIG).Digitizing error of data. ANALYSIS Charge dependence of the cross section for correlations between recoils measured by SAD and He fragments registered by FWD. -ENDBIB 5 +HISTORY (20110313A) SD: SF8=MSC in REACTION code added. +ENDBIB 7 COMMON 1 3 ERR-DIG MICRO-B @@ -756,15 +732,17 @@ MEV/A NO-DIM MICRO-B 300. 13. 23.3 300. 14. 16.2 ENDDATA 20 -ENDSUBENT 34 -SUBENT O1658019 20081117 20081219 20081219 O037 -BIB 3 5 -REACTION (1-H-2(14-SI-28,X)ELEM,,SIG) fig 9 +ENDSUBENT 36 +SUBENT O1658019 20110906 20111003 20110913 O045 +BIB 4 7 +REACTION (1-H-2(14-SI-28,X)ELEM,,SIG,,MSC) fig 9 + in coincidence with He in ang=3.9-11.7 deg ERR-ANALYS (ERR-DIG).Digitizing error of data. ANALYSIS Charge dependence of the cross section for correlations between recoils measured by SAD and He fragments registered by FWD. -ENDBIB 5 +HISTORY (20110313A) SD: SF8=MSC in REACTION code added. +ENDBIB 7 COMMON 1 3 ERR-DIG MICRO-B @@ -792,16 +770,20 @@ MEV/A NO-DIM MICRO-B 300. 13. 26. 300. 14. 12. ENDDATA 20 -ENDSUBENT 34 -SUBENT O1658020 20081117 20081219 20081219 O037 -BIB 4 6 -REACTION (1-H-2(14-SI-28,X)ELEM,,SIG) fig 10. +ENDSUBENT 36 +SUBENT O1658020 20110313 20111003 20110913 O045 +BIB 7 10 +REACTION (1-H-2(14-SI-28,X)ELEM,,SIG,,MSC) fig 10. + in coincidence with He detection +MONITOR (1-H-2(14-SI-28,X)1-H-2,,SIG) ERR-ANALYS (ERR-DIG).Digitizing error of data. ANALYSIS The dependence of the cross section for the correlations on the scattering angle of He fragment registered in different of the FWD. MISC-COL (MISC).The scattering angle of He fragment. -ENDBIB 6 +STATUS (CURVE) Fig.10 of Phys.Rev.C77(2008)044601 +HISTORY (20110313A) SD: SF8=MSC in REACTION code added. +ENDBIB 10 COMMON 3 3 EN MISC ERR-DIG MEV ADEG MICRO-B @@ -820,16 +802,20 @@ NO-DIM MICRO-B 13. 23. 14. 16. ENDDATA 11 -ENDSUBENT 26 -SUBENT O1658021 20081117 20081219 20081219 O037 -BIB 4 6 -REACTION (1-H-2(14-SI-28,X)ELEM,,SIG) fig 10. +ENDSUBENT 30 +SUBENT O1658021 20110313 20111003 20110913 O045 +BIB 7 10 +REACTION (1-H-2(14-SI-28,X)ELEM,,SIG,,MSC) fig 10. + in coincidence with He detection +MONITOR (1-H-2(14-SI-28,X)1-H-2,,SIG) ERR-ANALYS (ERR-DIG).Digitizing error of data. ANALYSIS The dependence of the cross section for the correlations on the scattering angle of He fragment registered in different of the FWD. MISC-COL (MISC).The scattering angle of He fragment. -ENDBIB 6 +STATUS (CURVE) Fig.10 of Phys.Rev.C77(2008)044601 +HISTORY (20110313A) SD: SF8=MSC in REACTION code added. +ENDBIB 10 COMMON 3 3 EN MISC ERR-DIG MEV ADEG MICRO-B @@ -848,16 +834,20 @@ NO-DIM MICRO-B 13. 3.2 14. 1.5 ENDDATA 11 -ENDSUBENT 26 -SUBENT O1658022 20081117 20081219 20081219 O037 -BIB 4 6 -REACTION (1-H-2(14-SI-28,X)ELEM,,SIG) fig 10. +ENDSUBENT 30 +SUBENT O1658022 20110313 20111003 20110913 O045 +BIB 7 10 +REACTION (1-H-2(14-SI-28,X)ELEM,,SIG,,MSC) fig 10. + in coincidence with He detection +MONITOR (1-H-2(14-SI-28,X)1-H-2,,SIG) ERR-ANALYS (ERR-DIG).Digitizing error of data. ANALYSIS The dependence of the cross section for the correlations on the scattering angle of He fragment registered in different of the FWD. MISC-COL (MISC).The scattering angle of He fragment. -ENDBIB 6 +HISTORY (20110313A) SD: SF8=MSC in REACTION code added. +STATUS (CURVE) Fig.10 of Phys.Rev.C77(2008)044601 +ENDBIB 10 COMMON 3 3 EN MISC ERR-DIG MEV ADEG MICRO-B @@ -876,17 +866,21 @@ NO-DIM MICRO-B 13. 2.53 14. 1.48 ENDDATA 11 -ENDSUBENT 26 -SUBENT O1658023 20081117 20081219 20081219 O037 -BIB 4 7 -REACTION (1-H-2(14-SI-28,X)ELEM,,SIG) fig 10. +ENDSUBENT 30 +SUBENT O1658023 20110313 20111003 20110913 O045 +BIB 7 11 +REACTION (1-H-2(14-SI-28,X)ELEM,,SIG,,MSC) fig 10. + in coincidence with He detection +MONITOR (1-H-2(14-SI-28,X)1-H-2,,SIG) ERR-ANALYS (DATA-ERR).The error is reported by authors on fig. (ERR-DIG).Digitizing error of data. ANALYSIS The dependence of the cross section for the correlations on the scattering angle of He fragment registered in different of the FWD. MISC-COL (MISC).The scattering angle of He fragment. -ENDBIB 7 +STATUS (CURVE) Fig.10 of Phys.Rev.C77(2008)044601 +HISTORY (20110313A) SD: SF8=MSC in REACTION code added. +ENDBIB 11 COMMON 3 3 EN MISC ERR-DIG MEV ADEG MICRO-B @@ -905,7 +899,7 @@ NO-DIM MICRO-B MICRO-B 13. 0.796 3.E-02 14. 0.466 3.E-02 ENDDATA 11 -ENDSUBENT 27 +ENDSUBENT 31 SUBENT O1658024 20081117 20081219 20081219 O037 BIB 3 5 REACTION (1-H-2(14-SI-28,X)ELEM,,SIG) fig 11. diff --git a/exforall/O18/O1891.x4 b/exforall/O18/O1891.x4 index 514feaa23..83db52a69 100644 --- a/exforall/O18/O1891.x4 +++ b/exforall/O18/O1891.x4 @@ -1,5 +1,5 @@ -ENTRY O1891 20110207 20110621 20110620 O044 -SUBENT O1891001 20110207 20110621 20110620 O044 +ENTRY O1891 20110913 20111003 20110913 O045 +SUBENT O1891001 20110913 20111003 20110913 O045 BIB 11 31 TITLE On the decay of the J= 11/2-, T1/2 = 38.9 h isomer in Ba-133- search for the E5 transition and @@ -11,7 +11,7 @@ INSTITUTE (2SF ABA) (2SF TKU) (2SF JYV) (2SF HLS) -REFERENCE (J,JP/G,38,015001,2011) +REFERENCE (J,JP/G,38,015101,2011) FACILITY (VDGT,2SF HLS) The Tandem van de Graaff at the Accelerator Laboratory at Helsinki University (ACCEL,2SF ABA) The actual activation study of the @@ -35,12 +35,12 @@ HISTORY (20110207C) sb ENDBIB 31 NOCOMMON 0 0 ENDSUBENT 34 -SUBENT O1891002 20110214 20110621 20110620 O044 +SUBENT O1891002 20110913 20111003 20110913 O045 BIB 3 4 REACTION (55-CS-133(P,N)56-BA-133-M,,SIG) DECAY-DATA (56-BA-133-M,38.9HR,DG,276.1,0.175) STATUS (CURVE).By CAJAD- Data scanned from Fig.2 - of J,JP/G,38,015001,201186. + of J,JP/G,38,015101,201186. ENDBIB 4 COMMON 2 3 EN-ERR-DIG ERR-DIG