| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 192.6 (b) | 191.3 (b) | 0.993 | − | 5.746 (b) | 7.581 (b) |
| 2 | (n,elastic) | 14.47 (b) | 16.15 (b) | 1.116 | − | 2.760 (b) | 4.560 (b) |
| 4 | (n,inelastic) | ( E-thr = 33.34 keV ) | 307.2 (mb) | 1.526 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.605 MeV ) | 522.4 (mb) | 2.356 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.37 MeV ) | 6.321 (mb) | 1.829 (μb) | |||
| 18 | (n,fission) | 20.19 (mb) | 19.73 (mb) | 0.977 | 5.368 (b) | 2.148 (b) | 1.336 (b) |
| 19 | (n,f) | 20.19 (mb) | 19.73 (mb) | 0.977 | 4.867 (b) | 855.5 (mb) | 1.312 (b) |
| 20 | (n,nf) | ( E-thr = 2.300 MeV ) | 1.038 (b) | 24.29 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 9.000 MeV ) | 254.1 (mb) | 33.84 (μb) | |||
| 37 | (n,4n) | ( E-thr = 19.38 MeV ) | − | 222.5e-18 (b) | |||
| 38 | (n,3nf) | ( E-thr = 15.00 MeV ) | − | 3.016 (nb) | |||
| 102 | (n,γ) | 178.1 (b) | 175.1 (b) | 0.983 | 701.1 (b) | 1.273 (mb) | 155.2 (mb) |
| 456 | νp | 2.615 | − | − | − | 4.618 | − |
| 455 | νd | 1.200e-2 | − | − | − | 8.000e-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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