| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 698.9 (b) | 686.2 (b) | 0.982 | − | 5.894 (b) | 7.628 (b) |
| 2 | (n,elastic) | 15.12 (b) | 16.95 (b) | 1.121 | − | 2.839 (b) | 4.451 (b) |
| 4 | (n,inelastic) | ( E-thr = 77.33 eV ) | 420.3 (mb) | 1.858 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.320 MeV ) | 548.2 (mb) | 12.43 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.19 MeV ) | 30.33 (mb) | 6.947 (μb) | |||
| 18 | (n,fission) | 585.1 (b) | 571.4 (b) | 0.977 | 274.4 (b) | 2.053 (b) | 1.218 (b) |
| 19 | (n,f) | 585.1 (b) | 571.4 (b) | 0.977 | 274.0 (b) | 780.9 (mb) | 1.201 (b) |
| 20 | (n,nf) | ( E-thr = 3.500 MeV ) | 766.4 (mb) | 16.78 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.500 MeV ) | 506.1 (mb) | 92.33 (μb) | |||
| 37 | (n,4n) | ( E-thr = 17.98 MeV ) | − | 161.4e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 14.50 MeV ) | − | 5.251 (nb) | |||
| 102 | (n,γ) | 98.71 (b) | 97.83 (b) | 0.991 | 139.0 (b) | 889.7 (μb) | 87.41 (mb) |
| 456 | νp | 2.420 | − | − | − | 4.497 | − |
| 455 | νd | 1.585e-2 | − | − | − | 9.425e-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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