| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 29.19 (b) | 30.80 (b) | 1.055 | − | 5.500 (b) | 6.801 (b) |
| 2 | (n,elastic) | 12.45 (b) | 14.05 (b) | 1.129 | − | 2.755 (b) | 4.616 (b) |
| 4 | (n,inelastic) | ( E-thr = 81.07 keV ) | 535.7 (mb) | 2.089 (b) | |||
| 16 | (n,2n) | ( E-thr = 8.527 MeV ) | 2.202 (b) | 2.583 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.22 MeV ) | − | 2.089 (μb) | |||
| 22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 667.0 (nb) | 58.96 (μb) | 36.05 (nb) |
| 28 | (n,np) | ( E-thr = 7.360 MeV ) | 71.83 (μb) | 35.76 (nb) | |||
| 32 | (n,nd) | ( E-thr = 13.21 MeV ) | 0.000 (b) | 8.774e-12 (b) | |||
| 102 | (n,γ) | 16.75 (b) | 16.75 (b) | 1.000 | 118.8 (b) | 1.933 (mb) | 94.16 (mb) |
| 103 | (n,p) | ( E-thr = 1.078 MeV ) | 5.375 (mb) | 2.732 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.122 MeV ) | 485.7 (μb) | 98.92 (nb) | |||
| 105 | (n,t) | ( E-thr = 6.916 MeV ) | 1.457 (μb) | 1.142 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 16.02 (μb) | 856.3 (μb) | 1.284 (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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