| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 2.939 (kb) | 3.003 (kb) | 1.022 | − | 5.894 (b) | 7.841 (b) |
| 2 | (n,elastic) | 9.657 (b) | 10.94 (b) | 1.133 | − | 2.871 (b) | 4.469 (b) |
| 4 | (n,inelastic) | ( E-thr = 56.24 keV ) | 302.5 (mb) | 1.207 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.761 MeV ) | 254.5 (mb) | 3.146 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.77 MeV ) | 284.6 (μb) | 403.0 (nb) | |||
| 18 | (n,fission) | 2.808 (kb) | 2.863 (kb) | 1.020 | 1.173 (kb) | 2.464 (b) | 2.096 (b) |
| 19 | (n,f) | 2.808 (kb) | 2.863 (kb) | 1.020 | 1.172 (kb) | 1.445 (b) | 2.083 (b) |
| 20 | (n,nf) | ( E-thr = 2.000 MeV ) | 924.9 (mb) | 12.42 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 8.000 MeV ) | 94.74 (mb) | 13.84 (μb) | |||
| 37 | (n,4n) | ( E-thr = 18.86 MeV ) | − | 154.0e-15 (b) | |||
| 38 | (n,3nf) | ( E-thr = 16.00 MeV ) | − | 14.63e-12 (b) | |||
| 102 | (n,γ) | 121.3 (b) | 129.2 (b) | 1.066 | 100.3 (b) | 1.008 (mb) | 64.84 (mb) |
| 456 | νp | 2.400 | − | − | − | 4.386 | − |
| 455 | νd | 7.040e-3 | − | − | − | 6.076e-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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