| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 4.708 (b) | 5.149 (b) | 1.094 | − | 4.974 (b) | 5.880 (b) |
| 2 | (n,elastic) | 3.415 (b) | 3.856 (b) | 1.129 | − | 3.457 (b) | 4.321 (b) |
| 4 | (n,inelastic) | ( E-thr = 35.79 keV ) | 182.0 (mb) | 1.496 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.630 MeV ) | 1.328 (b) | 8.808 (mb) | |||
| 17 | (n,3n) | ( E-thr = 16.14 MeV ) | − | 770.8 (nb) | |||
| 22 | (n,na) | ( E-thr = 2.257 MeV ) | 29.89 (μb) | 12.50 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.769 MeV ) | 13.87 (μb) | 31.49 (nb) | |||
| 32 | (n,nd) | ( E-thr = 12.96 MeV ) | 0.000 (b) | 234.1e-12 (b) | |||
| 102 | (n,γ) | 1.293 (b) | 1.293 (b) | 1.000 | 21.86 (b) | 1.000 (mb) | 52.52 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 80.36 (μb) | 4.846 (mb) | 3.959 (μb) |
| 104 | (n,d) | ( E-thr = 6.441 MeV ) | 547.0 (μb) | 129.8 (nb) | |||
| 105 | (n,t) | ( E-thr = 6.730 MeV ) | 7.672 (μb) | 8.861 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 46.01 (μb) | 2.392 (mb) | 6.063 (μb) |
|
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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