| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 6.084 (b) | 6.856 (b) | 1.127 | − | 4.480 (b) | 5.571 (b) |
| 2 | (n,elastic) | 6.010 (b) | 6.781 (b) | 1.128 | − | 2.512 (b) | 4.363 (b) |
| 4 | (n,inelastic) | ( E-thr = 517.6 keV ) | 343.0 (mb) | 1.181 (b) | |||
| 16 | (n,2n) | ( E-thr = 8.776 MeV ) | 1.623 (b) | 1.975 (mb) | |||
| 17 | (n,3n) | ( E-thr = 14.98 MeV ) | − | 5.146 (μb) | |||
| 22 | (n,na) | ( E-thr = 4.855 MeV ) | 375.3 (nb) | 932.3e-12 (b) | |||
| 28 | (n,np) | ( E-thr = 11.20 MeV ) | 29.08 (nb) | 1.905 (nb) | |||
| 102 | (n,γ) | 74.86 (mb) | 74.87 (mb) | 1.000 | 1.743 (b) | 1.002 (mb) | 21.49 (mb) |
| 103 | (n,p) | ( E-thr = 5.361 MeV ) | 1.788 (mb) | 404.2 (nb) | |||
| 104 | (n,d) | ( E-thr = 8.868 MeV ) | 314.2 (nb) | 3.915 (nb) | |||
| 105 | (n,t) | ( E-thr = 10.52 MeV ) | 5.894 (nb) | 986.8e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 20.92 (nb) | 67.82 (μb) | 16.52 (nb) |
|
These cross sections are calculated from JENDL-3.2 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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