| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 176.7 (b) | 177.4 (b) | 1.004 | − | 5.903 (b) | 7.919 (b) |
| 2 | (n,elastic) | 9.200 (b) | 10.37 (b) | 1.127 | − | 2.737 (b) | 4.455 (b) |
| 4 | (n,inelastic) | ( E-thr = 44.82 keV ) | 367.9 (mb) | 998.7 (mb) | |||
| 16 | (n,2n) | ( E-thr = 7.384 MeV ) | 218.9 (mb) | 257.7 (μb) | |||
| 17 | (n,3n) | ( E-thr = 13.65 MeV ) | 3.283 (μb) | 28.67 (nb) | |||
| 18 | (n,fission) | 140.0 (b) | 139.4 (b) | 0.996 | 971.0 (b) | 2.577 (b) | 2.359 (b) |
| 19 | (n,f) | 140.0 (b) | 139.4 (b) | 0.996 | 970.4 (b) | 1.036 (b) | 2.330 (b) |
| 20 | (n,nf) | ( E-thr = 800.0 keV ) | 1.523 (b) | 29.28 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 8.500 MeV ) | 19.59 (mb) | 6.031 (μb) | |||
| 38 | (n,3nf) | ( E-thr = 14.50 MeV ) | − | 1.538 (nb) | |||
| 102 | (n,γ) | 27.56 (b) | 27.61 (b) | 1.002 | 248.0 (b) | 1.056 (mb) | 104.3 (mb) |
| 456 | νp | 2.906 | − | − | − | 4.873 | − |
| 455 | νd | 2.248e-3 | − | − | − | 1.832e-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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