| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 109.2 (b) | 112.4 (b) | 1.030 | − | 4.976 (b) | 5.880 (b) |
| 2 | (n,elastic) | 24.12 (b) | 27.22 (b) | 1.128 | − | 3.458 (b) | 4.483 (b) |
| 4 | (n,inelastic) | ( E-thr = 80.82 keV ) | 128.3 (mb) | 1.345 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.667 MeV ) | 1.382 (b) | 9.428 (mb) | |||
| 17 | (n,3n) | ( E-thr = 16.00 MeV ) | − | 915.1 (nb) | |||
| 22 | (n,na) | ( E-thr = 2.578 MeV ) | 57.04 (μb) | 21.72 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.886 MeV ) | 10.20 (μb) | 31.09 (nb) | |||
| 32 | (n,nd) | ( E-thr = 13.08 MeV ) | 0.000 (b) | 228.6e-12 (b) | |||
| 102 | (n,γ) | 85.06 (b) | 85.18 (b) | 1.001 | 899.4 (b) | 1.000 (mb) | 40.98 (mb) |
| 103 | (n,p) | ( E-thr = 189.0 keV ) | 5.040 (mb) | 4.163 (μb) | |||
| 104 | (n,d) | ( E-thr = 6.558 MeV ) | 452.3 (μb) | 118.8 (nb) | |||
| 105 | (n,t) | ( E-thr = 6.843 MeV ) | 11.30 (μb) | 12.72 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 28.40 (μb) | 1.703 (mb) | 2.859 (μb) |
|
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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