| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 9.651 (b) | 10.32 (b) | 1.069 | − | 2.949 (b) | 3.666 (b) |
| 2 | (n,elastic) | 5.144 (b) | 5.807 (b) | 1.129 | − | 1.485 (b) | 2.839 (b) |
| 4 | (n,inelastic) | ( E-thr = 680.4 keV ) | 555.9 (mb) | 790.5 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.03 MeV ) | 489.7 (mb) | 86.87 (μb) | |||
| 22 | (n,na) | ( E-thr = 5.869 MeV ) | 16.43 (mb) | 4.345 (μb) | |||
| 28 | (n,np) | ( E-thr = 6.223 MeV ) | 310.5 (mb) | 609.2 (μb) | |||
| 32 | (n,nd) | ( E-thr = 14.73 MeV ) | − | 5.591 (nb) | |||
| 102 | (n,γ) | 4.507 (b) | 4.510 (b) | 1.000 | 5.009 (b) | 727.3 (μb) | 10.73 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 118.3 (mb) | 46.15 (mb) | 25.29 (mb) |
| 104 | (n,d) | ( E-thr = 3.963 MeV ) | 7.503 (mb) | 7.291 (μb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 9.816 (mb) | 37.00 (mb) | 555.5 (μb) |
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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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