| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 4.445 (b) | 4.991 (b) | 1.123 | − | 4.630 (b) | 5.709 (b) |
| 2 | (n,elastic) | 4.230 (b) | 4.776 (b) | 1.129 | − | 2.605 (b) | 4.815 (b) |
| 4 | (n,inelastic) | ( E-thr = 105.0 keV ) | 547.2 (mb) | 851.9 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.407 MeV ) | 1.468 (b) | 961.8 (μb) | |||
| 17 | (n,3n) | ( E-thr = 16.41 MeV ) | − | 122.2 (nb) | |||
| 22 | (n,na) | ( E-thr = 4.095 MeV ) | 20.24 (μb) | 14.43 (nb) | |||
| 28 | (n,np) | ( E-thr = 10.09 MeV ) | 16.34 (μb) | 34.20 (nb) | |||
| 102 | (n,γ) | 215.6 (mb) | 215.6 (mb) | 1.000 | 5.279 (b) | 934.9 (μb) | 39.79 (mb) |
| 103 | (n,p) | ( E-thr = 3.675 MeV ) | 6.816 (mb) | 2.215 (μb) | |||
| 104 | (n,d) | ( E-thr = 7.842 MeV ) | 128.7 (μb) | 43.53 (nb) | |||
| 105 | (n,t) | ( E-thr = 10.37 MeV ) | 1.648 (nb) | 196.0e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 9.880 MeV ) | 6.654e-18 (b) | 589.3e-18 (b) | |||
| 107 | (n,a) | 98.29e-27 (b) | 99.47e-27 (b) | 0.000 | 6.054 (μb) | 1.197 (mb) | 503.4 (nb) |
|
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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