| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 3.887 (b) | 4.332 (b) | 1.114 | − | 4.975 (b) | 5.882 (b) |
| 2 | (n,elastic) | 3.447 (b) | 3.891 (b) | 1.129 | − | 3.453 (b) | 4.891 (b) |
| 4 | (n,inelastic) | ( E-thr = 671.6 keV ) | 137.6 (mb) | 957.7 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.196 MeV ) | 1.378 (b) | 1.152 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.83 MeV ) | − | 1.814 (μb) | |||
| 22 | (n,na) | ( E-thr = 2.562 MeV ) | 23.80 (μb) | 8.577 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.181 MeV ) | 284.4 (nb) | 14.35 (nb) | |||
| 102 | (n,γ) | 440.1 (mb) | 440.2 (mb) | 1.000 | 7.954 (b) | 1.017 (mb) | 31.60 (mb) |
| 103 | (n,p) | ( E-thr = 2.905 MeV ) | 3.974 (mb) | 1.479 (μb) | |||
| 104 | (n,d) | ( E-thr = 6.852 MeV ) | 37.65 (μb) | 26.29 (nb) | |||
| 105 | (n,t) | ( E-thr = 9.402 MeV ) | 2.015 (nb) | 2.187 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 21.85 (μb) | 1.786 (mb) | 1.366 (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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