| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 91.81 (b) | 92.19 (b) | 1.004 | − | 2.770 (b) | 3.997 (b) |
| 2 | (n,elastic) | 2.305 (b) | 2.602 (b) | 1.129 | − | 1.311 (b) | 2.893 (b) |
| 4 | (n,inelastic) | ( E-thr = 345.2 keV ) | 471.9 (mb) | 993.6 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.153 MeV ) | 450.1 (mb) | 272.4 (μb) | |||
| 22 | (n,na) | ( E-thr = 6.206 MeV ) | 4.262 (mb) | 997.4 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.746 MeV ) | 332.9 (mb) | 99.46 (μb) | |||
| 32 | (n,nd) | ( E-thr = 15.20 MeV ) | − | 507.1e-12 (b) | |||
| 102 | (n,γ) | 75.60 (b) | 75.65 (b) | 1.001 | 119.8 (b) | 928.9 (μb) | 2.608 (mb) |
| 103 | (n,p) | 1.448 (b) | 1.447 (b) | 1.000 | 2.786 (b) | 138.1 (mb) | 90.49 (mb) |
| 104 | (n,d) | ( E-thr = 6.483 MeV ) | 11.81 (mb) | 4.843 (μb) | |||
| 105 | (n,t) | ( E-thr = 8.839 MeV ) | 178.6 (μb) | 27.92 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 7.970 MeV ) | 2.973 (μb) | 981.3e-12 (b) | |||
| 107 | (n,a) | 12.46 (b) | 12.46 (b) | 1.001 | 19.34 (b) | 46.88 (mb) | 16.03 (mb) |
|
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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