| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 237.1 (b) | 239.2 (b) | 1.009 | − | 5.849 (b) | 7.745 (b) |
| 2 | (n,elastic) | 11.83 (b) | 13.35 (b) | 1.129 | − | 2.741 (b) | 4.420 (b) |
| 4 | (n,inelastic) | ( E-thr = 51.95 keV ) | 415.6 (mb) | 829.6 (mb) | |||
| 16 | (n,2n) | ( E-thr = 7.701 MeV ) | 173.6 (mb) | 138.0 (μb) | |||
| 17 | (n,3n) | ( E-thr = 13.81 MeV ) | 12.63 (μb) | 216.5 (nb) | |||
| 18 | (n,fission) | 25.01 (b) | 25.01 (b) | 1.000 | 503.7 (b) | 2.518 (b) | 2.409 (b) |
| 19 | (n,f) | 25.01 (b) | 25.01 (b) | 1.000 | 503.3 (b) | 1.391 (b) | 2.388 (b) |
| 20 | (n,nf) | ( E-thr = 1.900 MeV ) | 1.125 (b) | 20.96 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 9.500 MeV ) | 3.472 (mb) | 3.066 (μb) | |||
| 38 | (n,3nf) | ( E-thr = 16.00 MeV ) | − | 44.66e-12 (b) | |||
| 102 | (n,γ) | 200.1 (b) | 200.0 (b) | 1.000 | 137.7 (b) | 783.4 (μb) | 84.75 (mb) |
| 456 | νp | 2.356 | − | − | − | 3.756 | − |
| 455 | νd | 2.397e-3 | − | − | − | 1.667e-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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