| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 22.95 (b) | 23.93 (b) | 1.043 | − | 4.334 (b) | 5.669 (b) |
| 2 | (n,elastic) | 6.938 (b) | 7.826 (b) | 1.128 | − | 2.837 (b) | 5.051 (b) |
| 4 | (n,inelastic) | ( E-thr = 392.8 keV ) | 219.4 (mb) | 602.9 (mb) | |||
| 16 | (n,2n) | ( E-thr = 8.531 MeV ) | 1.249 (b) | 1.781 (mb) | |||
| 22 | (n,na) | ( E-thr = 7.391 MeV ) | 1.737 (μb) | 7.058 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.534 MeV ) | 1.413 (mb) | 353.7 (nb) | |||
| 32 | (n,nd) | ( E-thr = 15.95 MeV ) | − | 11.24e-12 (b) | |||
| 102 | (n,γ) | 16.01 (b) | 16.10 (b) | 1.006 | 121.0 (b) | 1.002 (mb) | 10.87 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 5.274 (mb) | 19.52 (mb) | 601.6 (μb) |
| 104 | (n,d) | ( E-thr = 7.197 MeV ) | 1.455 (mb) | 300.7 (nb) | |||
| 105 | (n,t) | ( E-thr = 9.696 MeV ) | 252.8 (nb) | 3.306 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 10.37 MeV ) | 1.897e-15 (b) | 2.881e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 452.8 (μb) | 5.761 (mb) | 28.33 (μb) |
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These cross sections are calculated from JENDL-3.3 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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