| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 22.01 (b) | 23.19 (b) | 1.053 | − | 5.469 (b) | 6.771 (b) |
| 2 | (n,elastic) | 9.137 (b) | 10.31 (b) | 1.129 | − | 2.709 (b) | 4.645 (b) |
| 4 | (n,inelastic) | ( E-thr = 91.95 keV ) | 715.5 (mb) | 1.757 (b) | |||
| 16 | (n,2n) | ( E-thr = 8.901 MeV ) | 2.030 (b) | 1.741 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.84 MeV ) | − | 869.0 (nb) | |||
| 22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 1.785 (μb) | 149.0 (μb) | 99.34 (nb) |
| 28 | (n,np) | ( E-thr = 6.896 MeV ) | 170.7 (μb) | 60.72 (nb) | |||
| 102 | (n,γ) | 12.88 (b) | 12.88 (b) | 1.000 | 166.2 (b) | 1.630 (mb) | 368.0 (mb) |
| 103 | (n,p) | ( E-thr = 232.1 keV ) | 7.404 (mb) | 5.874 (μb) | |||
| 104 | (n,d) | ( E-thr = 4.658 MeV ) | 794.9 (μb) | 171.0 (nb) | |||
| 105 | (n,t) | ( E-thr = 6.820 MeV ) | 2.322 (μb) | 1.578 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 50.71 (μb) | 1.538 (mb) | 4.781 (μb) |
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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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