| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 92.25 (b) | 93.38 (b) | 1.012 | − | 5.965 (b) | 8.005 (b) |
| 2 | (n,elastic) | 10.90 (b) | 12.16 (b) | 1.116 | − | 2.750 (b) | 4.899 (b) |
| 4 | (n,inelastic) | ( E-thr = 43.17 keV ) | 429.0 (mb) | 2.378 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.856 MeV ) | 757.3 (mb) | 22.67 (mb) | |||
| 17 | (n,3n) | ( E-thr = 10.59 MeV ) | 470.6 (mb) | 106.0 (μb) | |||
| 18 | (n,fission) | 21.37 (mb) | 21.38 (mb) | 1.001 | 2.719 (b) | 1.552 (b) | 666.2 (mb) |
| 19 | (n,f) | 21.37 (mb) | 21.38 (mb) | 1.001 | 2.408 (b) | 516.6 (mb) | 644.5 (mb) |
| 20 | (n,nf) | ( E-thr = 2.000 MeV ) | 683.6 (mb) | 21.75 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 8.000 MeV ) | 352.7 (mb) | 51.05 (μb) | |||
| 37 | (n,4n) | ( E-thr = 16.83 MeV ) | − | 14.35 (nb) | |||
| 38 | (n,3nf) | ( E-thr = 12.50 MeV ) | 5.514 (nb) | 200.4 (nb) | |||
| 102 | (n,γ) | 81.33 (b) | 81.20 (b) | 0.998 | 868.6 (b) | 998.1 (μb) | 34.00 (mb) |
| 456 | νp | 3.356 | − | − | − | 6.436 | − |
| 455 | νd | 4.404e-2 | − | − | − | 2.987e-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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