| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 11.71 (b) | 12.88 (b) | 1.099 | − | 5.535 (b) | 6.836 (b) |
| 2 | (n,elastic) | 8.985 (b) | 10.14 (b) | 1.129 | − | 2.770 (b) | 4.641 (b) |
| 4 | (n,inelastic) | ( E-thr = 80.28 keV ) | 467.2 (mb) | 2.155 (b) | |||
| 16 | (n,2n) | ( E-thr = 7.818 MeV ) | 2.292 (b) | 5.380 (mb) | |||
| 17 | (n,3n) | ( E-thr = 14.29 MeV ) | − | 5.975 (μb) | |||
| 22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 72.13 (nb) | 12.96 (μb) | 6.269 (nb) |
| 28 | (n,np) | ( E-thr = 8.044 MeV ) | 17.34 (μb) | 16.71 (nb) | |||
| 32 | (n,nd) | ( E-thr = 13.13 MeV ) | 0.000 (b) | 10.66e-12 (b) | |||
| 102 | (n,γ) | 2.730 (b) | 2.731 (b) | 1.001 | 38.31 (b) | 1.897 (mb) | 35.06 (mb) |
| 103 | (n,p) | ( E-thr = 1.948 MeV ) | 3.777 (mb) | 1.289 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.806 MeV ) | 287.0 (μb) | 59.91 (nb) | |||
| 105 | (n,t) | ( E-thr = 6.837 MeV ) | 1.482 (μb) | 1.088 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 3.289 (μb) | 404.9 (μb) | 250.2 (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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