| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 1.028 (kb) | 1.110 (kb) | 1.080 | − | 5.933 (b) | 7.835 (b) |
| 2 | (n,elastic) | 8.813 (b) | 9.728 (b) | 1.104 | − | 2.944 (b) | 4.396 (b) |
| 4 | (n,inelastic) | ( E-thr = 7.894 keV ) | 416.4 (mb) | 1.581 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.670 MeV ) | 229.6 (mb) | 3.325 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.70 MeV ) | 2.318 (mb) | 988.9 (nb) | |||
| 18 | (n,fission) | 747.4 (b) | 790.5 (b) | 1.058 | 301.0 (b) | 2.334 (b) | 1.802 (b) |
| 19 | (n,f) | 747.4 (b) | 790.5 (b) | 1.058 | 300.6 (b) | 1.079 (b) | 1.781 (b) |
| 20 | (n,nf) | ( E-thr = 1.100 MeV ) | 958.0 (mb) | 20.89 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.000 MeV ) | 297.1 (mb) | 53.67 (μb) | |||
| 37 | (n,4n) | ( E-thr = 18.60 MeV ) | − | 1.949e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 15.50 MeV ) | − | 196.8e-12 (b) | |||
| 102 | (n,γ) | 271.5 (b) | 310.1 (b) | 1.142 | 179.7 (b) | 847.4 (μb) | 52.61 (mb) |
| 456 | νp | 2.872 | − | − | − | 4.935 | − |
| 455 | νd | 6.220e-3 | − | − | − | 4.260e-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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