| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 7.812 (kb) | 7.743 (kb) | 0.991 | − | 5.975 (b) | 8.046 (b) |
| 2 | (n,elastic) | 8.940 (b) | 9.132 (b) | 1.021 | − | 2.737 (b) | 4.469 (b) |
| 4 | (n,inelastic) | ( E-thr = 24.92 keV ) | 385.6 (mb) | 2.216 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.129 MeV ) | 228.9 (mb) | 18.69 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.78 MeV ) | 32.11 (mb) | 4.256 (μb) | |||
| 18 | (n,fission) | 4.939 (kb) | 4.895 (kb) | 0.991 | 1.033 (kb) | 2.586 (b) | 1.280 (b) |
| 19 | (n,f) | 4.939 (kb) | 4.895 (kb) | 0.991 | 1.032 (kb) | 1.389 (b) | 1.269 (b) |
| 20 | (n,nf) | ( E-thr = 2.300 MeV ) | 1.115 (b) | 11.44 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.500 MeV ) | 84.08 (mb) | 16.00 (μb) | |||
| 37 | (n,4n) | ( E-thr = 17.39 MeV ) | − | 522.5e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 14.50 MeV ) | − | 1.112 (nb) | |||
| 102 | (n,γ) | 2.864 (kb) | 2.839 (kb) | 0.991 | 518.8 (b) | 807.0 (μb) | 61.58 (mb) |
| 456 | νp | 4.100 | − | − | − | 7.264 | − |
| 455 | νd | 5.900e-3 | − | − | − | 4.060e-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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