| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 20.38 (b) | 22.02 (b) | 1.080 | − | 5.859 (b) | 7.716 (b) |
| 2 | (n,elastic) | 13.04 (b) | 14.72 (b) | 1.128 | − | 2.740 (b) | 4.832 (b) |
| 4 | (n,inelastic) | ( E-thr = 49.58 keV ) | 468.1 (mb) | 2.690 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.468 MeV ) | 1.766 (b) | 16.76 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.61 MeV ) | 521.9 (mb) | 72.39 (μb) | |||
| 18 | (n,fission) | 53.71 (μb) | 53.80 (μb) | 1.002 | 374.7 (mb) | 361.1 (mb) | 79.94 (mb) |
| 19 | (n,f) | 53.71 (μb) | 53.80 (μb) | 1.002 | 264.7 (mb) | 118.8 (mb) | 74.72 (mb) |
| 20 | (n,nf) | ( E-thr = 2.700 MeV ) | 197.7 (mb) | 5.214 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 8.500 MeV ) | 44.61 (mb) | 7.378 (μb) | |||
| 37 | (n,4n) | ( E-thr = 18.43 MeV ) | − | 731.2e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 14.00 MeV ) | 0.000 (b) | 9.799 (nb) | |||
| 102 | (n,γ) | 7.338 (b) | 7.300 (b) | 0.995 | 84.29 (b) | 1.136 (mb) | 95.98 (mb) |
| 456 | νp | 1.851 | − | − | − | 3.897 | − |
| 455 | νd | 4.900e-2 | − | − | − | 3.228e-2 | − |
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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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