| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 10.20 (b) | 11.10 (b) | 1.089 | − | 5.957 (b) | 7.999 (b) |
| 2 | (n,elastic) | 6.989 (b) | 7.889 (b) | 1.129 | − | 2.400 (b) | 4.811 (b) |
| 4 | (n,inelastic) | ( E-thr = 43.58 keV ) | 411.9 (mb) | 2.040 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.238 MeV ) | 680.3 (mb) | 9.356 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.42 MeV ) | 199.8 (mb) | 26.71 (μb) | |||
| 18 | (n,fission) | 336.6 (mb) | 336.6 (mb) | 1.000 | 7.837 (b) | 2.260 (b) | 1.090 (b) |
| 19 | (n,f) | 336.6 (mb) | 336.6 (mb) | 1.000 | 7.152 (b) | 469.9 (mb) | 1.052 (b) |
| 20 | (n,nf) | ( E-thr = 1.300 MeV ) | 1.601 (b) | 38.05 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.000 MeV ) | 189.1 (mb) | 27.06 (μb) | |||
| 37 | (n,4n) | ( E-thr = 17.90 MeV ) | − | 653.7e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 13.50 MeV ) | 78.60 (μb) | 126.9 (nb) | |||
| 102 | (n,γ) | 2.872 (b) | 2.879 (b) | 1.002 | 266.7 (b) | 1.053 (mb) | 46.46 (mb) |
| 456 | νp | 3.110 | − | − | − | 6.022 | − |
| 455 | νd | 1.960e-2 | − | − | − | 1.340e-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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