| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 19.52 (b) | 20.15 (b) | 1.032 | − | 3.341 (b) | 4.230 (b) |
| 2 | (n,elastic) | 4.815 (b) | 5.435 (b) | 1.129 | − | 1.801 (b) | 2.776 (b) |
| 4 | (n,inelastic) | 0.000 (b) | 0.000 (b) | − | 5.400 (b) | 281.9 (mb) | 1.437 (b) |
| 16 | (n,2n) | ( E-thr = 6.877 MeV ) | 1.229 (b) | 2.225 (mb) | |||
| 17 | (n,3n) | ( E-thr = 17.78 MeV ) | − | 19.60 (nb) | |||
| 22 | (n,na) | ( E-thr = 5.381 MeV ) | 1.572 (mb) | 335.8 (nb) | |||
| 24 | (n,2na) | ( E-thr = 11.95 MeV ) | 233.2e-15 (b) | 876.1e-12 (b) | |||
| 28 | (n,np) | ( E-thr = 10.14 MeV ) | 1.719 (mb) | 443.2 (nb) | |||
| 41 | (n,2np) | ( E-thr = 16.75 MeV ) | − | 17.38e-12 (b) | |||
| 102 | (n,γ) | 14.71 (b) | 14.71 (b) | 1.000 | 62.95 (b) | 699.3 (μb) | 15.09 (mb) |
| 103 | (n,p) | ( E-thr = 822.2 keV ) | 20.22 (mb) | 86.73 (μb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 1.128 (mb) | 6.850 (mb) | 118.3 (μb) |
| 112 | (n,pa) | ( E-thr = 7.299 MeV ) | 469.7e-12 (b) | 3.243e-12 (b) | |||
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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 :
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