This repository contains woking version of new thermal-resonance ranges information table (thermal-res-table.txt) released from CoNDERC homepage (https://nds.iaea.org/conderc).
- Each of na.dat, nel.dat, ng.dat, np.dat file contains (n,a), (n,el), (n,g), (n,f) and (n,p) reaction data.
- Evaluated data are extracted from thermal-res-table.txt released from CoNDERC homepage (https://nds.iaea.org/conderc).
- EXFOR data are extracted from 'EXFOR-2020-10-28.bck.c5' file that was distributed by Viktor on Oct.2020.
- For the cross section data (sf6 = SIG), incident neutron energy range is from 0.0235 eV +/- 5%.
- In the EXFOR data table, the coulums are:
- dataset: EXFOR entry+subentry number
- firstauthor: Name of first author
- year: Year of the publication
- sf4: Reaction product
- sf5: Reaction branch
- sf8: Reaction modifiers
- sf9: Data type
- en: Incident neutron energy (somethimes average of between MIN and MAX)
- den: Uncertainty of incident neutron enery (en)
- ydata: Cross section in barn
- yddata: Uncertainty of cross section (ydata) in barn
- Summary table (resulttable.dat) contains Evaluated data, EXFOR mean value, and EXFOR MXW/SPA data mean for each nuclides.
91-Pa-231 (n,g)
# Evaluated data
# Maxw.(n,g) | (n,g)
# NAN (+/- NAN) | 2.00E+02 (+/- 2.30E+00) **<--- Read from the 'thermal-res-table.txt'.**
# EXFOR data mean
# 2.40E+02 (+/- 9.50E+00) **<--- Calculated from EXFOR data by exclusion of the case where the reaction product is in an isomeric state.**
# EXFOR MXW/SPA data mean
# 2.11E+02 (+/- 2.00E+01) **<--- Calculated from EXFOR MXW/SPA data flagged in sf8.**
# ------ EXFOR data ------
dataset firstauthor year sf4 sf8 sf9 en den ydata yddata
40163002 B.M.Aleksandrov+ 1972 91-PA-232 -- -- 2.53E-02 NAN 2.60E+02 1.30E+01
40579003 L.N.Jurova+ 1984 91-PA-232 -- -- 2.53E-02 NAN 2.19E+02 6.00E+00
# ------ MXW/SPA data ------
dataset firstauthor year sf4 sf8 sf9 en den ydata yddata
12273002 R.R.Smith+ 1956 91-PA-232 MXW -- 2.53E-02 NAN 2.00E+02 1.50E+01
20634002 E.M.Gryntakis+ 1974 91-PA-232 MXW -- 2.53E-02 NAN 2.01E+02 2.20E+01
20634002 E.M.Gryntakis+ 1974 91-PA-232 MXW -- 2.53E-02 NAN 2.18E+02 1.40E+01
20691003 K.Kobayashi 1974 91-PA-232 MXW -- 2.53E-02 NAN 2.01E+02 6.03E+00
23227002 T.Hashimoto+ 1988 91-PA-232 MXW -- 2.53E-02 NAN 1.86E+02 1.30E+01
12287002 G.T.Seaborg+ 1946 91-PA-232 SPA -- 2.53E-02 NAN 1.75E+02 2.62E+01
12272002 R.Elson+ 1953 91-PA-232 SPA -- 2.53E-02 NAN 2.93E+02 4.40E+01
# ------ Recom./Eval./Deriv. data ------
dataset firstauthor year sf4 sf8 sf9 en den ydata yddata
V1002566 S.F.Mughabghab 2006 91-PA-232 -- RECOM 2.53E-02 NAN 2.01E+02 2.30E+00
- Summary table is resulttable.dat.
- For (n,g) reaction, both Evaluated and Evaluated(MXW) taken from 'thermal-res-table.txt' are listed in column 3-6.
- target: target nuclide in Z-Element-A format. If it is isomeric state, -M or -M2 is addded afterward.
- reaction: so far, reactions are (n,g), (n,el), (n,a), (n,p), (n,f) only.
- Eval.: Evaluated data taken from 'thermal-res-table.txt'.
- Eval-err: Error of evaluated data taken from 'thermal-res-table.txt'.
- Eval(MXW): Evaluated(MXW) data taken from 'thermal-res-table.txt'. only in (n,g).
- Eval(MXW)-err: Error of evaluated(MXW) data taken from 'thermal-res-table.txt'. only in (n,g).
- EXFOR-data-mean: Mean value of EXFOR data.
- EXFOR-mean-err: Mean value of EXFOR data error.
- MXW-data-mean: Mean value of EXFOR data measured in MXW or SPA specified in sf8.
- MXW-mean-err: Mean value of EXFOR data error measured in MXW or SPA specified in sf8.
target reaction Eval. Eval-err Eval(MXW) Eval(MXW)-err EXFOR-data-mean EXFOR-mean-err MXW-data-mean MXW-mean-err
1-H-1 (n,g) NAN NAN 3.33E-01 7.00E-04 3.01E+00 2.36E-01 3.11E-01 6.23E-03
1-H-2 (n,g) 5.08E-04 1.50E-05 NAN NAN 4.99E-04 1.82E-05 6.30E-04 6.10E-05
2-He-3 (n,g) 5.50E-05 3.00E-06 NAN NAN 4.05E-05 7.93E-06 6.88E-05 1.50E-05
2-He-4 (n,g) NAN NAN NAN NAN NAN NAN NAN NAN
3-Li-6 (n,g) 3.93E-02 7.00E-04 NAN NAN 3.93E-02 7.00E-04 3.81E-02 7.26E-03
3-Li-7 (n,g) 4.42E-02 5.00E-04 NAN NAN 4.43E-02 5.00E-04 4.01E-02 7.60E-03
4-Be-7 (n,g) NAN NAN NAN NAN NAN NAN 1.55E-01 NAN
- For the other reactions, Evaluated MXW data (Eval(MXW) and Eval(MXW)-err) are always NaN.
target reaction Eval. EEval-err Eval(MXW) Eval(MXW)-err EXFOR-data-mean EXFOR-mean-err MXW-data-mean MXW-mean-err
2-He-3 (n,p) 5.33E+03 8.00E+00 NAN NAN 5.66E+03 1.00E+03 5.04E+03 2.00E+02
4-Be-7 (n,p) 3.88E+04 8.09E+02 NAN NAN 4.63E+04 3.71E+03 4.68E+04 4.05E+03
5-B-10 (n,p) NAN NAN NAN NAN NAN NAN 6.40E-03 1.47E-03
7-N-14 (n,p) 1.86E+00 3.00E-02 NAN NAN 1.91E+00 4.85E-02 1.74E+00 4.17E-02
11-Na-22 (n,p) 2.78E+04 2.40E+03 NAN NAN NAN NAN 3.06E+04 2.60E+03
13-Al-26 (n,p) 1.97E+00 1.00E-02 NAN NAN NAN NAN NAN NAN
16-S-33 (n,p) 2.00E+00 1.00E+00 NAN NAN NAN NAN 2.61E-02 2.00E-01
17-Cl-35 (n,p) 4.89E-01 1.40E-02 NAN NAN 4.89E-01 1.40E-02 3.96E-01 4.10E-02
17-Cl-36 (n,p) 4.62E-02 4.00E-04 NAN NAN 2.24E-01 5.10E-02 NAN NAN
18-Ar-36 (n,p) NAN NAN NAN NAN NAN NAN 1.50E-03 8.10E-06
18-Ar-37 (n,p) 3.70E+01 4.00E+00 NAN NAN NAN NAN 4.60E+01 7.33E+00
2021 9th Jan. Shin