2024-11-29

exforall/100/10031.x4

@@ -1,9 +1,10 @@
-ENTRY            10031   19990719   19990812   20050926       0000
-SUBENT        10031001   19990719   19990812   20050926       0000
-BIB                 13         33
+ENTRY            10031   20241001   20241129   20241129       1515
+SUBENT        10031001   20241001   20241129   20241129       1515
+BIB                 13         38
 INSTITUTE  (1USALRL,1USASTF)
-REFERENCE  (J,NP/A,138,387,196912)
-AUTHOR     (R.C.BARRALL,M.SILBERGELD,D.G.GARDNER)
+REFERENCE  (J,NP/A,138,387,1969)
+           #doi:10.1016/0375-9474(69)90342-X
+AUTHOR     (R.C.Barrall,M.Silbergeld,D.G.Gardner)
 TITLE      Cross sections of some reactions of Al, S, Mn, Fe, Ni,
            In, and I with 14.8 MeV neutrons.
 FACILITY   (ICTR,1USALRL) Insulated-core transformer accelerator.
@@ -29,33 +30,38 @@ ERR-ANALYS (DATA-ERR) Estimated two-standard deviation limits
             to each other, cross sections believed to be accurate
             to about 3%.
 STATUS     (APRVD) Approved by author
+           (TABLE,,R.C.Barrall+,J,NP/A,138,387,1969)
+            Data from Table 2 in reference
 HISTORY    (19691222C)
            (19800723A) Converted to REACTION formalism
            (19830803A) INSTITUTE corrected
            (19860613A) BIB updates.
            (19990719A) Converted to new date formats, lower case.
-ENDBIB              33
+           (20240930A) OS. Correction in sub.2, updated STATUS,
+            BIB updates
+ENDBIB              38
 COMMON               2          3
 EN         EN-RSL
 MEV        MEV
 14.8       .2
 ENDCOMMON            3
-ENDSUBENT           40
-SUBENT        10031002   19990719   19990812   20050926       0000
-BIB                  3          5
+ENDSUBENT           45
+SUBENT        10031002   20241001   20241129   20241129       1515
+BIB                  4          6
 REACTION   (13-AL-27(N,A)11-NA-24,,SIG)
 SAMPLE     Metal foil, 7.6 x 7.6 cm, with thickness 0.1 cm or
            less.
-DECAY-DATA (11-NA-24,,DG,13700.,1.00)
+DECAY-DATA (11-NA-24,,DG,1370.,1.00)
             Saturation activity (10**(-18)dps/nucleus) = 1.1717.
-ENDBIB               5
+HISTORY    (20240930A) DECAY-DATA corrected
+ENDBIB               6
 NOCOMMON             0          0
 DATA                 2          1
 DATA       DATA-ERR
 MB         MB
 116.       8.
 ENDDATA              3
-ENDSUBENT           13
+ENDSUBENT           14
 SUBENT        10031003   19990719   19990812   20050926       0000
 BIB                  3          3
 REACTION   (16-S-32(N,P)15-P-32,,SIG)

exforall/100/10056.x4

@@ -1,8 +1,8 @@
-ENTRY            10056   20101014   20110113   20110112       1367
-SUBENT        10056001   20101014   20110113   20110112       1367
-BIB                 13         24
+ENTRY            10056   20241001   20241129   20241129       1515
+SUBENT        10056001   20241001   20241129   20241129       1515
+BIB                 13         25
 INSTITUTE  (1USALAS)
-REFERENCE  (R,LA-4420,21,197006)
+REFERENCE  (R,LA-4420,21,1970)
 AUTHOR     (D.W.Bergen)
 TITLE      Fission cross sections from POMMARD.
 INC-SOURCE (EXPLO) Pommard.
@@ -15,7 +15,7 @@ DETECTOR   (SOLST) Solid state detector in current recording mode.
 CORRECTION No correction for target contamination or for source-
             resolution function.
 ERR-ANALYS (ERR-T) Standard deviation
-           (ERR-SYS,,,1.0) Correlated error
+           (ERR-SYS,,,C) Correlated error
 STATUS     (APRVD) Approved by author.
            (TABLE) Data received on magnetic tape from P.A.
             Seeger, August, 1970.
@@ -25,9 +25,10 @@ HISTORY    (19710408C)
            (20101014A) VM: BIB updates. Error correlation factor
                        added. Subentry 002 updated; moved some
                        data to subentries 003,004,005.
-ENDBIB              24
+           (20240930A) OS. ERR-ANALYS code modified
+ENDBIB              25
 NOCOMMON             0          0
-ENDSUBENT           27
+ENDSUBENT           28
 SUBENT        10056002   20101014   20110113   20110112       1367
 BIB                  5          8
 REACTION   (92-U-233(N,F),,SIG)

exforall/101/10134.x4

@@ -1,10 +1,11 @@
-ENTRY            10134   20140605   20141007   20141003       1400
-SUBENT        10134001   20140605   20141007   20141003       1400
-BIB                 10         18
-AUTHOR     (R.L.Bramlett,J.B.Czirr)
+ENTRY            10134   20241001   20241129   20241129       1515
+SUBENT        10134001   20241001   20241129   20241129       1515
+BIB                 10         20
+AUTHOR     (R.L.Bramblett,J.B.Czirr)
 TITLE      Energy-Dependent Shielding Factors for 235U Foils
            from Transmission Measurements
 REFERENCE  (J,NSE,35,350,1969)
+           #doi:10.13182/NSE69-A20013
 INSTITUTE  (1USALRL)
 FACILITY   (LINAC,1USALRL) 33 MeV electron linear accelerator.
 INC-SOURCE (PHOTO)
@@ -19,9 +20,10 @@ HISTORY    (19720524C)
            (19820527A) converted to reaction formalism
            (20000321A) converted to new date format, lower case.
            (20140605A) BP: Added experimental data.
-ENDBIB              18
+           (20240930A) OS. Author name corrected
+ENDBIB              20
 NOCOMMON             0          0
-ENDSUBENT           21
+ENDSUBENT           23
 SUBENT        10134002   20140605   20141007   20141003       1400
 BIB                  5          8
 REACTION   (92-U-235(N,F),,SIG,,AV)

exforall/101/10184.x4

@@ -1,9 +1,10 @@
-ENTRY            10184   20101018   20110216   20110117       1369
-SUBENT        10184001   20101018   20110216   20110117       1369
-BIB                 13         51
+ENTRY            10184   20241001   20241129   20241129       1515
+SUBENT        10184001   20241001   20241129   20241129       1515
+BIB                 13         54
 INSTITUTE  (1USAWIS,1USAANL)
-REFERENCE  (J,PR/C,4,1061,197110)
-           (J,BAP,16,1180,197110)
+REFERENCE  (J,PR/C,4,1061,1971)
+           #doi:10.1103/PhysRevC.4.1061
+           (J,BAP,16,1180(ED2),1971)
 AUTHOR     (J.C.Davis,K.A.Weaver,D.Hilscher,H.H.Barschall,
            A.B.Smith)
 TITLE      Total Cross Section of Protons for 2.5 MeV Neutrons.
@@ -32,27 +33,29 @@ CORRECTION Transmissions corrected for background, counting
             scattering.
 ERR-ANALYS (ERR-SYS) Systematic uncertainty
             RMS of following uncertainties (in %)
-           (ERR-1,,,1.0) energy determination        0.07
-           (ERR-2,,,1.0) sample density              0.06
-           (ERR-3,,,1.0) sample container length     0.05
-           (ERR-4,,,1.0) sample purity               0.03
-           (ERR-5,,,1.0) neutron background          0.02
-           (ERR-6,,,1.0) counting losses             0.02
-           (ERR-7,,,1.0) number of atoms in graphite 0.02
-           (ERR-8,,,1.0) inscattering                0.01
+           (ERR-1) energy determination        0.07
+           (ERR-2) sample density              0.06
+           (ERR-3) sample container length     0.05
+           (ERR-4) sample purity               0.03
+           (ERR-5) neutron background          0.02
+           (ERR-6) counting losses             0.02
+           (ERR-7) number of atoms in graphite 0.02
+           (ERR-8) inscattering                0.01
            (ERR-S) Statistical uncertainty.
             Standard deviation (which includes any instabilities
             in detector or electronics) -2.3 mb.
            (ERR-T) Total uncertainty.
 STATUS     (APRVD) Approved by author.
-           (TABLE) Data taken from Table IV of main reference.
+           (TABLE,,J.C.Davis+,J,PR/C,4,1061,1971)
+            Data taken from Table IV of main reference.
 HISTORY    (19711203C)
            (19750902A) BIB changes
            (19820916A) Converted to REACTION formalism
            (20010214A) Converted to new date formats, lower case.
            (20101018A) VM: Error heading update.
                        Correction to 10184.002.
-ENDBIB              51
+           (20240930A) OS. REFERENCE code corrected
+ENDBIB              54
 COMMON               8          6
 ERR-1      ERR-2      ERR-3      ERR-4      ERR-5      ERR-6
 ERR-7      ERR-8
@@ -61,7 +64,7 @@ PER-CENT   PER-CENT
  0.07       0.06       0.05       0.03       0.02       0.02
  0.02       0.01
 ENDCOMMON            6
-ENDSUBENT           61
+ENDSUBENT           64
 SUBENT        10184002   20101018   20110216   20110117       1369
 BIB                  2          3
 REACTION   (1-H-1(N,TOT),,SIG)

exforall/101/10189.x4

@@ -1,13 +1,14 @@
-ENTRY            10189   20010214   20010404   20050926       0000
-SUBENT        10189001   20010214   20010404   20050926       0000
-BIB                 14         23
+ENTRY            10189   20241001   20241129   20241129       1515
+SUBENT        10189001   20241001   20241129   20241129       1515
+BIB                 14         26
 INSTITUTE  (1USAGEO)
-REFERENCE  (J,PR/C,6,1181,197210)
-           (J,BAP,16,1163,1971)
-AUTHOR     (F.D.MCDANIEL,M.W.MCDONALD,M.F.STEUER,R.M.WOOD)
+REFERENCE  (J,PR/C,6,1181,1972)
+           #doi:10.1103/PhysRevC.6.1181
+           (J,BAP,16,1163(CC1),1971)
+AUTHOR     (F.D.McDaniel,M.W.McDonald,M.F.Steuer,R.M.Wood)
 TITLE      Spin-Flip Probability in the Inelastic Scattering
             of 7.48 MeV Neutrons from the 4.43 MeV State in 12C
-FACILITY   (VDG) 5.5-MeV Van-de-Graaff in pulsed and
+FACILITY   (VDG,1USAGEO) 5.5-MeV Van-de-Graaff in pulsed and
             bunched beam modes
 INC-SOURCE (D-D)
 SAMPLE     Cylindrical sample of natural graphite,
@@ -18,32 +19,36 @@ MONITOR    (6-C-0(N,EL)6-C-0,,SIG)
 CORRECTION Corrected for multiple scattering by method of Cox
             and for flux attenuation.
 ERR-ANALYS (ERR-S) Errors given are statistical errors only.
-STATUS     (APRVD) APPROVED BY AUTHOR
+STATUS     (APRVD) Approved by author
 HISTORY    (19720424C)
            (19740108U) BIB changes.
            (19820916A) Converted to REACTION formalism
            (20010214A) Converted to new date formats, lower case.
               SF4 added to reactions; error heading corrected.
-ENDBIB              23
+           (20240930A) OS. REFERENCE corrected, STATUS coding
+            updated, BIB updates, Data headings corrected
+ENDBIB              26
 COMMON               1          3
 MONIT
 MB
  1304.
 ENDCOMMON            3
-ENDSUBENT           30
-SUBENT        10189002   20010214   20010404   20050926       0000
-BIB                  3          3
+ENDSUBENT           33
+SUBENT        10189002   20241001   20241129   20241129       1515
+BIB                  3          5
 REACTION   (6-C-0(N,EL)6-C-0,,DA)
-STATUS     Tabulated data received from F.McDaniel, November 1971.
+STATUS     (TABLE) Tabulated data received from F.McDaniel,
+            November 1971.
 HISTORY    (19750707A) Isotope corrected
-ENDBIB               3
+           (20240930A) DATA -> DATA-CM
+ENDBIB               5
 COMMON               1          3
 EN
 MEV
        7.48
 ENDCOMMON            3
 DATA                 3         13
-ANG-CM     DATA       ERR-S
+ANG-CM     DATA-CM    ERR-S
 ADEG       MB/SR      MB/SR
        32.4      330.3        0.2
        43.1      220.9        0.2
@@ -59,19 +64,21 @@ ADEG       MB/SR      MB/SR
       143.1      117.2        0.3
       152.4      129.9        0.3
 ENDDATA             15
-ENDSUBENT           27
-SUBENT        10189003   20010214   20010404   20050926       0000
-BIB                  2          2
+ENDSUBENT           29
+SUBENT        10189003   20241001   20241129   20241129       1515
+BIB                  3          4
 REACTION   (6-C-12(N,INL)6-C-12,PAR,DA)
-STATUS     Tabulated data received from F.McDaniel, May 1972.
-ENDBIB               2
+STATUS     (TABLE) Tabulated data received from F.McDaniel,
+            May 1972.
+HISTORY    (20240930A) DATA -> DATA-CM
+ENDBIB               4
 COMMON               2          3
 EN         E-LVL
 MEV        MEV
        7.48       4.43
 ENDCOMMON            3
 DATA                 3         13
-ANG-CM     DATA       ERR-S
+ANG-CM     DATA-CM    ERR-S
 ADEG       MB/SR      MB/SR
       34.0       12.04        .10
       45.15      16.40        .14
@@ -87,5 +94,5 @@ ADEG       MB/SR      MB/SR
      145.14      24.51        .19
      154.0       26.59        .19
 ENDDATA             15
-ENDSUBENT           26
+ENDSUBENT           28
 ENDENTRY             3

exforall/101/10199.x4

@@ -1,9 +1,9 @@
-ENTRY            10199   20010214   20010404   20050926       0000
-SUBENT        10199001   20010214   20010404   20050926       0000
-BIB                 12         22
+ENTRY            10199   20241001   20241129   20241129       1515
+SUBENT        10199001   20241001   20241129   20241129       1515
+BIB                 12         28
 INSTITUTE  (1USAROC,1USANWU)
-REFERENCE  (C,69VIENNA,,403(118),196907)
-AUTHOR     (J.R.HUIZENGA,A.N.BEHKAMI,J.H.ROBERTS)
+REFERENCE  (C,69VIENNA,,403,1969)
+AUTHOR     (J.R.Huizenga,A.N.Behkami,J.H.Roberts)
 TITLE      Channel analysis of neutron-induced fission of 236U
 FACILITY   (VDG,1USAANL) 3-MeV Van-de-Graaff at ANL
 INC-SOURCE (P-LI7)
@@ -12,20 +12,26 @@ SAMPLE     Isotopic composition -  U-234 (0.0015%),
                                    U-236 (99.76%),
                                    U-238 (0.043%).
            Sample thickness - 0.5 mg/cm**2.
+           (92-U-234,ENR=0.000015)
+           (92-U-235,ENR=0.00192)
+           (92-U-236,ENR=0.9976)
+           (92-U-238,ENR=0.00043)
 DETECTOR   (TRD) Polycarbonate resin detector
 CORRECTION Corrected for angular resolution (9 degr)
            Not corrected for fission induced by neutrons
             scattered from chamber walls or components, or for
             fission due to 235U (both estimated small).
-ERR-ANALYS (DATA-ERR) no information on source of uncertainties.
+ERR-ANALYS (DATA-ERR) No information on source of uncertainties.
 STATUS     (APRVD) Approved by author.
-           Data taken from table in reference.
+           (TABLE,,J.R.Huizenga+,C,69VIENNA,,403,1969)
+            Data taken from table in reference.
 HISTORY    (19740530C)
            (19820921A) Converted to REACTION formalism
            (20010214A) Converted to new date formats, lower case.
-ENDBIB              22
+           (20240930A) OS. REFERENCE corrected, BIB updates
+ENDBIB              28
 NOCOMMON             0          0
-ENDSUBENT           25
+ENDSUBENT           31
 SUBENT        10199002   20010214   20010404   20050926       0000
 BIB                  1          1
 REACTION   (92-U-236(N,F),,DA,FF,REL)

exforall/103/10327.x4

@@ -1,8 +1,9 @@
-ENTRY            10327   20020926   20021120   20050926       0000
-SUBENT        10327001   20020926   20021120   20050926       0000
-BIB                 13         21
+ENTRY            10327   20241001   20241129   20241129       1515
+SUBENT        10327001   20241001   20241129   20241129       1515
+BIB                 13         23
 INSTITUTE  (1USALRL)
 REFERENCE  (J,NP/A,265,77,1976)
+           #doi:10.1016/0375-9474(76)90116-0
 AUTHOR     (M.A.Gardner,D.G.Gardner)
 TITLE      Structure in the 27Al(n,alpha)24Na cross section
             around 14 MeV
@@ -22,16 +23,20 @@ HISTORY    (19740513C)
            (19771206A) BIB update. Converted to REACTION
              formalism.
            (20020926A) Updated to new date formats, lower case.
-ENDBIB              21
+           (20240930A) OS. DECAY-DATA in sub.2 corrected
+ENDBIB              23
 NOCOMMON             0          0
-ENDSUBENT           24
-SUBENT        10327002   20020926   20021120   20050926       0000
-BIB                  4          4
+ENDSUBENT           26
+SUBENT        10327002   20241001   20241129   20241129       1515
+BIB                  5          7
 REACTION   (13-AL-27(N,A)11-NA-24,,SIG,,REL)
-DECAY-DATA (11-NA-24,15.HR,DG,1.368)
+DECAY-DATA (11-NA-24,15.HR,DG,1368.)
 ERR-ANALYS No information on uncertainties.
-STATUS     Tabulated data received from D. Gardner, August 1973.
-ENDBIB               4
+STATUS     (TABLE) Tabulated data received from D. Gardner,
+            August 1973.
+HISTORY    (20240930A) DECAY-DATA energy corrected, STATUS code
+            added
+ENDBIB               7
 COMMON               1          3
 EN-RSL
 KEV
@@ -135,5 +140,5 @@ MEV        ARB-UNITS
  14.880     44.26
  14.895     44.27
 ENDDATA             96
-ENDSUBENT          109
+ENDSUBENT          112
 ENDENTRY             2