| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 11.72 (b) | 12.74 (b) | 1.087 | − | 2.949 (b) | 3.690 (b) |
| 2 | (n,elastic) | 7.931 (b) | 8.954 (b) | 1.129 | − | 1.476 (b) | 2.888 (b) |
| 4 | (n,inelastic) | ( E-thr = 680.4 keV ) | 559.6 (mb) | 775.1 (mb) | |||
| 16 | (n,2n) | ( E-thr = 10.06 MeV ) | 607.9 (mb) | 158.0 (μb) | |||
| 22 | (n,na) | ( E-thr = 5.869 MeV ) | 11.62 (mb) | 3.081 (μb) | |||
| 28 | (n,np) | ( E-thr = 6.223 MeV ) | 219.4 (mb) | 427.1 (μb) | |||
| 32 | (n,nd) | ( E-thr = 14.73 MeV ) | − | 4.165 (nb) | |||
| 102 | (n,γ) | 3.786 (b) | 3.788 (b) | 1.000 | 4.149 (b) | 657.3 (μb) | 9.484 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 83.72 (mb) | 38.93 (mb) | 17.67 (mb) |
| 104 | (n,d) | ( E-thr = 3.963 MeV ) | 6.314 (mb) | 5.482 (μb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 6.926 (mb) | 28.87 (mb) | 390.2 (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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