| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 3.385 (kb) | 3.388 (kb) | 1.001 | − | 4.976 (b) | 5.883 (b) |
| 2 | (n,elastic) | 3.645 (b) | 4.113 (b) | 1.128 | − | 3.457 (b) | 4.579 (b) |
| 4 | (n,inelastic) | 0.000 (b) | 0.000 (b) | − | 3.825 (b) | 175.1 (mb) | 1.147 (b) |
| 16 | (n,2n) | ( E-thr = 6.345 MeV ) | 1.339 (b) | 9.898 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.54 MeV ) | − | 1.751 (μb) | |||
| 22 | (n,na) | ( E-thr = 2.909 MeV ) | 9.936 (μb) | 6.472 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.250 MeV ) | 139.9 (nb) | 14.19 (nb) | |||
| 32 | (n,nd) | ( E-thr = 13.20 MeV ) | 0.000 (b) | 113.8e-12 (b) | |||
| 102 | (n,γ) | 3.381 (kb) | 3.381 (kb) | 1.000 | 1.338 (kb) | 1.000 (mb) | 146.1 (mb) |
| 103 | (n,p) | ( E-thr = 804.9 keV ) | 2.517 (mb) | 1.276 (μb) | |||
| 104 | (n,d) | ( E-thr = 6.921 MeV ) | 259.6 (μb) | 74.03 (nb) | |||
| 105 | (n,t) | ( E-thr = 6.962 MeV ) | 11.26 (μb) | 10.43 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 9.646 (μb) | 1.336 (mb) | 934.9 (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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