| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 22.61 (b) | 24.71 (b) | 1.093 | − | 6.157 (b) | 7.554 (b) |
| 2 | (n,elastic) | 9.823 (b) | 11.07 (b) | 1.127 | − | 3.131 (b) | 5.481 (b) |
| 4 | (n,inelastic) | ( E-thr = 68.00 keV ) | 588.4 (mb) | 1.936 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.422 MeV ) | 755.7 (mb) | 26.69 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.34 MeV ) | 1.670 (b) | 253.8 (μb) | |||
| 18 | (n,fission) | 7.003 (μb) | 7.004 (μb) | 1.000 | 2.739 (mb) | 11.50 (mb) | 338.0 (μb) |
| 37 | (n,4n) | ( E-thr = 17.86 MeV ) | − | 142.8 (nb) | |||
| 102 | (n,γ) | 12.79 (b) | 13.64 (b) | 1.066 | 282.3 (b) | 31.97 (μb) | 108.5 (mb) |
| 456 | νp | 1.266 | − | − | − | 3.072 | − |
| 455 | νd | 5.321e-2 | − | − | − | 2.334e-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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