| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 8.572 (b) | 9.659 (b) | 1.127 | − | 3.447 (b) | 4.267 (b) |
| 2 | (n,elastic) | 8.418 (b) | 9.504 (b) | 1.129 | − | 1.883 (b) | 3.115 (b) |
| 4 | (n,inelastic) | 0.000 (b) | 0.000 (b) | − | 3.928 (b) | 395.8 (mb) | 1.148 (b) |
| 16 | (n,2n) | ( E-thr = 9.554 MeV ) | 1.164 (b) | 697.2 (μb) | |||
| 17 | (n,3n) | ( E-thr = 16.15 MeV ) | − | 197.8 (nb) | |||
| 22 | (n,na) | ( E-thr = 7.609 MeV ) | 2.521 (μb) | 4.236 (nb) | |||
| 24 | (n,2na) | ( E-thr = 16.61 MeV ) | − | 93.01e-21 (b) | |||
| 28 | (n,np) | ( E-thr = 12.20 MeV ) | 44.84 (μb) | 29.63 (nb) | |||
| 102 | (n,γ) | 154.7 (mb) | 154.7 (mb) | 1.000 | 1.348 (b) | 429.2 (μb) | 2.722 (mb) |
| 103 | (n,p) | ( E-thr = 6.310 MeV ) | 3.373 (mb) | 1.074 (μb) | |||
| 107 | (n,a) | ( E-thr = 2.185 MeV ) | 402.6 (μb) | 155.8 (nb) | |||
| 112 | (n,pa) | ( E-thr = 14.99 MeV ) | − | 126.5e-21 (b) | |||
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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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