| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 7.498 (b) | 8.319 (b) | 1.109 | − | 3.973 (b) | 5.754 (b) |
| 2 | (n,elastic) | 6.356 (b) | 7.176 (b) | 1.129 | − | 2.229 (b) | 4.478 (b) |
| 4 | (n,inelastic) | ( E-thr = 30.73 keV ) | 349.8 (mb) | 1.246 (b) | |||
| 16 | (n,2n) | ( E-thr = 8.922 MeV ) | 1.335 (b) | 1.489 (mb) | |||
| 17 | (n,3n) | ( E-thr = 16.90 MeV ) | − | 213.7 (nb) | |||
| 22 | (n,na) | ( E-thr = 1.968 MeV ) | 2.262 (mb) | 1.474 (μb) | |||
| 28 | (n,np) | ( E-thr = 6.105 MeV ) | 11.17 (mb) | 4.603 (μb) | |||
| 102 | (n,γ) | 1.142 (b) | 1.143 (b) | 1.000 | 8.982 (b) | 1.002 (mb) | 28.42 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 3.998 (mb) | 29.98 (mb) | 294.5 (μb) |
| 104 | (n,d) | ( E-thr = 3.856 MeV ) | 5.913 (mb) | 3.195 (μb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 1.013 (mb) | 7.339 (mb) | 79.47 (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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