| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 2.185 (kb) | 2.118 (kb) | 0.969 | − | 5.969 (b) | 8.127 (b) |
| 2 | (n,elastic) | 6.245 (b) | 6.785 (b) | 1.086 | − | 3.021 (b) | 4.585 (b) |
| 4 | (n,inelastic) | ( E-thr = 62.74 keV ) | 278.7 (mb) | 1.711 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.608 MeV ) | 367.4 (mb) | 7.285 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.60 MeV ) | 6.073 (mb) | 1.687 (μb) | |||
| 18 | (n,fission) | 1.673 (kb) | 1.620 (kb) | 0.969 | 2.218 (kb) | 2.290 (b) | 1.737 (b) |
| 19 | (n,f) | 1.673 (kb) | 1.620 (kb) | 0.969 | 2.217 (kb) | 1.436 (b) | 1.726 (b) |
| 20 | (n,nf) | ( E-thr = 2.100 MeV ) | 627.7 (mb) | 11.14 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 8.000 MeV ) | 226.1 (mb) | 37.51 (μb) | |||
| 37 | (n,4n) | ( E-thr = 18.66 MeV ) | − | 5.946e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 15.50 MeV ) | − | 110.4e-12 (b) | |||
| 102 | (n,γ) | 506.5 (b) | 491.2 (b) | 0.970 | 695.9 (b) | 823.7 (μb) | 85.83 (mb) |
| 456 | νp | 4.060 | − | − | − | 7.056 | − |
| 455 | νd | 2.800e-3 | − | − | − | 1.900e-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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