| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 4.481 (b) | 5.041 (b) | 1.125 | − | 4.797 (b) | 5.850 (b) |
| 2 | (n,elastic) | 4.345 (b) | 4.905 (b) | 1.129 | − | 2.809 (b) | 4.999 (b) |
| 4 | (n,inelastic) | ( E-thr = 105.0 keV ) | 357.0 (mb) | 840.0 (mb) | |||
| 16 | (n,2n) | ( E-thr = 8.557 MeV ) | 1.630 (b) | 2.560 (mb) | |||
| 17 | (n,3n) | ( E-thr = 14.55 MeV ) | − | 1.635 (μb) | |||
| 22 | (n,na) | ( E-thr = 6.742 MeV ) | 1.540 (nb) | 70.05e-12 (b) | |||
| 28 | (n,np) | ( E-thr = 12.20 MeV ) | 8.103e-12 (b) | 1.145 (nb) | |||
| 102 | (n,γ) | 135.7 (mb) | 135.6 (mb) | 1.000 | 7.862 (b) | 915.8 (μb) | 6.011 (mb) |
| 103 | (n,p) | ( E-thr = 6.631 MeV ) | 292.9 (μb) | 76.77 (nb) | |||
| 104 | (n,d) | ( E-thr = 9.955 MeV ) | 490.3 (nb) | 4.399 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.63 MeV ) | 80.39e-15 (b) | 23.95e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 14.48 MeV ) | − | 21.59e-24 (b) | |||
| 107 | (n,a) | ( E-thr = 1.542 MeV ) | 11.03 (μb) | 4.238 (nb) | |||
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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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