| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 64.90 (b) | 66.70 (b) | 1.028 | − | 6.015 (b) | 8.277 (b) |
| 2 | (n,elastic) | 9.319 (b) | 10.53 (b) | 1.130 | − | 2.843 (b) | 4.678 (b) |
| 4 | (n,inelastic) | ( E-thr = 46.58 keV ) | 308.5 (mb) | 2.721 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.998 MeV ) | 511.7 (mb) | 8.922 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.11 MeV ) | 286.3 (mb) | 43.05 (μb) | |||
| 18 | (n,fission) | 500.4 (mb) | 502.9 (mb) | 1.005 | 2.922 (b) | 2.060 (b) | 703.5 (mb) |
| 19 | (n,f) | 500.4 (mb) | 502.9 (mb) | 1.005 | 2.467 (b) | 919.6 (mb) | 680.8 (mb) |
| 20 | (n,nf) | ( E-thr = 2.100 MeV ) | 1.046 (b) | 22.75 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 8.500 MeV ) | 94.07 (mb) | 13.32 (μb) | |||
| 37 | (n,4n) | ( E-thr = 17.49 MeV ) | − | 814.3e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 13.50 MeV ) | 691.6e-18 (b) | 27.01 (nb) | |||
| 102 | (n,γ) | 55.00 (b) | 55.43 (b) | 1.008 | 1.386 (kb) | 897.7 (μb) | 163.6 (mb) |
| 456 | νp | 3.866 | − | − | − | 7.366 | − |
| 455 | νd | 8.776e-3 | − | − | − | 5.999e-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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