| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 2.132 (kb) | 2.081 (kb) | 0.976 | − | 5.973 (b) | 8.048 (b) |
| 2 | (n,elastic) | 2.247 (b) | 2.002 (b) | 0.891 | − | 2.736 (b) | 4.810 (b) |
| 4 | (n,inelastic) | ( E-thr = 42.89 keV ) | 404.6 (mb) | 1.686 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.652 MeV ) | 339.3 (mb) | 2.469 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.26 MeV ) | 21.52 (mb) | 3.225 (μb) | |||
| 18 | (n,fission) | 112.0 (b) | 105.0 (b) | 0.937 | 133.4 (b) | 2.466 (b) | 1.489 (b) |
| 19 | (n,f) | 112.0 (b) | 105.0 (b) | 0.937 | 133.2 (b) | 1.780 (b) | 1.482 (b) |
| 20 | (n,nf) | ( E-thr = 2.300 MeV ) | 662.6 (mb) | 7.513 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 9.500 MeV ) | 25.46 (mb) | 4.337 (μb) | |||
| 37 | (n,4n) | ( E-thr = 19.26 MeV ) | − | 76.38e-15 (b) | |||
| 38 | (n,3nf) | ( E-thr = 14.50 MeV ) | − | 1.398 (nb) | |||
| 102 | (n,γ) | 2.018 (kb) | 1.974 (kb) | 0.978 | 11.90 (kb) | 952.0 (μb) | 57.44 (mb) |
| 456 | νp | 3.630 | − | − | − | 6.710 | − |
| 455 | νd | 4.060e-3 | − | − | − | 2.800e-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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