| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 1.211 (kb) | 1.213 (kb) | 1.002 | − | 5.925 (b) | 8.292 (b) |
| 2 | (n,elastic) | 10.62 (b) | 11.99 (b) | 1.129 | − | 2.735 (b) | 4.391 (b) |
| 4 | (n,inelastic) | ( E-thr = 5.523 keV ) | 439.8 (mb) | 1.645 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.119 MeV ) | 175.4 (mb) | 2.152 (mb) | |||
| 17 | (n,3n) | ( E-thr = 13.69 MeV ) | 4.077 (μb) | 18.33 (nb) | |||
| 18 | (n,fission) | 1.000 (kb) | 999.5 (b) | 0.999 | 853.5 (b) | 2.570 (b) | 2.213 (b) |
| 19 | (n,f) | 1.000 (kb) | 999.5 (b) | 0.999 | 853.4 (b) | 1.844 (b) | 2.207 (b) |
| 20 | (n,nf) | ( E-thr = 2.300 MeV ) | 624.6 (mb) | 6.304 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 8.000 MeV ) | 102.6 (mb) | 16.72 (μb) | |||
| 38 | (n,3nf) | ( E-thr = 16.50 MeV ) | − | 205.2e-15 (b) | |||
| 102 | (n,γ) | 200.1 (b) | 199.9 (b) | 0.999 | 79.41 (b) | 808.8 (μb) | 38.25 (mb) |
| 456 | νp | 3.390 | − | − | − | 5.714 | − |
| 455 | νd | 1.460e-3 | − | − | − | 1.020e-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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