| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 6.510 (b) | 7.339 (b) | 1.127 | − | 1.495 (b) | 2.834 (b) |
| 2 | (n,elastic) | 6.503 (b) | 7.331 (b) | 1.127 | − | 960.2 (mb) | 2.673 (b) |
| 4 | (n,inelastic) | ( E-thr = 8.784 MeV ) | 22.90 (mb) | 38.95 (μb) | |||
| 6 | ( E-thr = 2.701 MeV ) | 168.6 (mb) | 66.50 (mb) | ||||
| 7 | ( E-thr = 7.561 MeV ) | 28.68 (mb) | 133.4 (μb) | ||||
| 16 | (n,2n) | ( E-thr = 1.868 MeV ) | 269.1 (mb) | 53.83 (mb) | |||
| 24 | (n,2na) | ( E-thr = 1.749 MeV ) | 17.49 (mb) | 4.938 (mb) | |||
| 46 | ( E-thr = 2.701 MeV ) | 168.6 (mb) | 66.50 (mb) | ||||
| 47 | ( E-thr = 7.561 MeV ) | 28.68 (mb) | 133.4 (μb) | ||||
| 102 | (n,γ) | 7.600 (mb) | 7.603 (mb) | 1.000 | 3.420 (mb) | 323.3 (nb) | 1.156 (μb) |
| 103 | (n,p) | ( E-thr = 14.26 MeV ) | − | 20.25 (nb) | |||
| 104 | (n,d) | ( E-thr = 16.30 MeV ) | − | 32.68 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.61 MeV ) | 18.36 (mb) | 2.751 (μb) | |||
| 107 | (n,a) | ( E-thr = 669.7 keV ) | 9.419 (mb) | 35.65 (mb) | |||
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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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