| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 1.315 (b) | 1.400 (b) | 1.065 | − | 2.291 (b) | 2.994 (b) |
| 2 | (n,elastic) | 655.4 (mb) | 739.9 (mb) | 1.129 | − | 788.0 (mb) | 2.569 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.498 MeV ) | 636.2 (mb) | 422.7 (mb) | |||
| 16 | (n,2n) | ( E-thr = 10.12 MeV ) | 835.7 (mb) | 304.1 (μb) | |||
| 17 | (n,3n) | ( E-thr = 16.88 MeV ) | − | 53.87 (nb) | |||
| 22 | (n,na) | ( E-thr = 6.968 MeV ) | 2.123 (mb) | 1.711 (μb) | |||
| 28 | (n,np) | ( E-thr = 12.84 MeV ) | 6.636 (μb) | 51.76 (nb) | |||
| 102 | (n,γ) | 660.1 (mb) | 660.5 (mb) | 1.001 | 293.3 (mb) | 346.5 (μb) | 1.013 (mb) |
| 103 | (n,p) | ( E-thr = 6.885 MeV ) | 14.99 (mb) | 19.52 (μb) | |||
| 104 | (n,d) | ( E-thr = 10.56 MeV ) | 1.949 (mb) | 326.5 (nb) | |||
| 105 | (n,t) | ( E-thr = 12.42 MeV ) | 354.1 (nb) | 1.736 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 15.41 MeV ) | − | 295.7e-15 (b) | |||
| 107 | (n,a) | ( E-thr = 2.548 MeV ) | 11.08 (mb) | 204.0 (μb) | |||
|
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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