| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 10.45 (b) | 11.64 (b) | 1.114 | − | 5.926 (b) | 8.023 (b) |
| 2 | (n,elastic) | 9.222 (b) | 10.41 (b) | 1.129 | − | 2.066 (b) | 4.721 (b) |
| 4 | (n,inelastic) | ( E-thr = 43.03 keV ) | 397.7 (mb) | 1.973 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.484 MeV ) | 670.5 (mb) | 5.644 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.03 MeV ) | 56.66 (mb) | 7.677 (μb) | |||
| 18 | (n,fission) | 44.01 (mb) | 44.14 (mb) | 1.003 | 7.599 (b) | 2.732 (b) | 1.250 (b) |
| 19 | (n,f) | 44.01 (mb) | 44.14 (mb) | 1.003 | 7.106 (b) | 1.196 (b) | 1.227 (b) |
| 20 | (n,nf) | ( E-thr = 1.403 MeV ) | 1.399 (b) | 23.13 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 9.000 MeV ) | 135.2 (mb) | 19.97 (μb) | |||
| 38 | (n,3nf) | ( E-thr = 13.50 MeV ) | 9.414 (μb) | 41.51 (nb) | |||
| 102 | (n,γ) | 1.179 (b) | 1.186 (b) | 1.006 | 113.1 (b) | 1.122 (mb) | 70.45 (mb) |
| 456 | νp | 2.980 | − | − | − | 5.181 | − |
| 455 | νd | 9.160e-3 | − | − | − | 6.400e-3 | − |
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These cross sections are calculated from JENDL-4.0 at 300K.
The background color of each cell noted a cross section means the order of the cross-section value.
The unit of cross section, (b), means barns, and SI prefixes are used as following.
(kb) → 103(b), (mb) → 10−3(b),
(μb) → 10−6(b), (nb) → 10−9(b).
MT is a number that defines a reaction type. For the relation between MT and reaction type, please see here or refer to the manual of ENDF formats.
Maxwellian Average :
where T denotes the temperature, and kB the Boltzmann constant.
The upper and lower limits of integration, EL and EU
are set to 10−5 eV and 10 eV, respectively.
Resonance Integral :
with EL = 0.5 eV and EU = 10 MeV.
U-235 Thermal Fission-Neutron Spectrum Average (Fiss. Spec. Average) :
with EL = 10−5 eV and EU = 20 MeV.
The parameters a and b are 0.988 MeV and 2.249 MeV−1, respectively.
Westcott g-factor :
νp,
νd
: numbers of prompt and delayed neutrons per fission.
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