| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 2.964 (Mb) | 3.523 (Mb) | 1.188 | − | 4.976 (b) | 5.887 (b) |
| 2 | (n,elastic) | 299.5 (kb) | 434.1 (kb) | 1.449 | − | 3.457 (b) | 4.874 (b) |
| 4 | (n,inelastic) | ( E-thr = 290.7 keV ) | 131.7 (mb) | 988.8 (mb) | |||
| 16 | (n,2n) | ( E-thr = 6.505 MeV ) | 1.384 (b) | 10.63 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.11 MeV ) | − | 2.107 (μb) | |||
| 22 | (n,na) | ( E-thr = 3.755 MeV ) | 6.775 (μb) | 6.050 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.903 MeV ) | 437.7e-12 (b) | 7.597 (nb) | |||
| 32 | (n,nd) | ( E-thr = 13.77 MeV ) | 0.000 (b) | 46.13e-12 (b) | |||
| 102 | (n,γ) | 2.665 (Mb) | 3.089 (Mb) | 1.159 | 7.597 (kb) | 1.000 (mb) | 10.47 (mb) |
| 103 | (n,p) | ( E-thr = 1.942 MeV ) | 1.028 (mb) | 362.9 (nb) | |||
| 104 | (n,d) | ( E-thr = 7.576 MeV ) | 103.3 (μb) | 52.87 (nb) | |||
| 105 | (n,t) | ( E-thr = 7.534 MeV ) | 8.034 (μb) | 13.02 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 2.461 (μb) | 1.227 (mb) | 382.7 (nb) |
|
These cross sections are calculated from JENDL-3.3 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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