| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 21.57 (b) | 22.89 (b) | 1.062 | − | 5.961 (b) | 8.293 (b) |
| 2 | (n,elastic) | 9.920 (b) | 11.20 (b) | 1.129 | − | 2.749 (b) | 4.523 (b) |
| 4 | (n,inelastic) | ( E-thr = 26.33 keV ) | 407.8 (mb) | 2.506 (b) | |||
| 16 | (n,2n) | ( E-thr = 4.732 MeV ) | 495.2 (mb) | 36.47 (mb) | |||
| 17 | (n,3n) | ( E-thr = 10.97 MeV ) | 263.7 (mb) | 43.25 (μb) | |||
| 18 | (n,fission) | 10.00 (b) | 10.01 (b) | 1.001 | 437.7 (b) | 2.041 (b) | 1.212 (b) |
| 19 | (n,f) | 10.00 (b) | 10.01 (b) | 1.001 | 437.3 (b) | 856.7 (mb) | 1.197 (b) |
| 20 | (n,nf) | ( E-thr = 2.100 MeV ) | 590.8 (mb) | 15.00 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 6.000 MeV ) | 593.9 (mb) | 206.3 (μb) | |||
| 37 | (n,4n) | ( E-thr = 16.15 MeV ) | − | 41.97 (nb) | |||
| 38 | (n,3nf) | ( E-thr = 12.50 MeV ) | 574.7e-15 (b) | 32.53 (nb) | |||
| 102 | (n,γ) | 1.601 (b) | 1.602 (b) | 1.001 | 56.87 (b) | 736.7 (μb) | 14.52 (mb) |
| 456 | νp | 3.320 | − | − | − | 6.316 | − |
| 455 | νd | 2.880e-2 | − | − | − | 1.960e-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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