| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 12.38 (b) | 12.91 (b) | 1.043 | − | 2.284 (b) | 3.137 (b) |
| 2 | (n,elastic) | 4.054 (b) | 4.578 (b) | 1.129 | − | 945.1 (mb) | 2.505 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.004 MeV ) | 812.4 (mb) | 630.1 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.87 MeV ) | 429.2 (mb) | 63.63 (μb) | |||
| 22 | (n,na) | ( E-thr = 9.646 MeV ) | 19.02 (μb) | 30.47 (nb) | |||
| 28 | (n,np) | ( E-thr = 11.69 MeV ) | 5.150 (mb) | 1.547 (μb) | |||
| 102 | (n,γ) | 8.328 (b) | 8.332 (b) | 1.001 | 3.714 (b) | 330.8 (μb) | 2.234 (mb) |
| 103 | (n,p) | ( E-thr = 3.276 MeV ) | 60.12 (mb) | 286.5 (μb) | |||
| 104 | (n,d) | ( E-thr = 9.415 MeV ) | 1.200 (mb) | 219.0 (nb) | |||
| 105 | (n,t) | ( E-thr = 13.89 MeV ) | 0.000 (b) | 400.5e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 12.46 MeV ) | 4.800e-15 (b) | 19.90e-12 (b) | |||
| 107 | (n,a) | ( E-thr = 2.074 MeV ) | 33.00 (mb) | 22.80 (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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