| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 7.379 (b) | 8.297 (b) | 1.124 | − | 4.337 (b) | 5.676 (b) |
| 2 | (n,elastic) | 7.150 (b) | 8.068 (b) | 1.128 | − | 2.599 (b) | 4.658 (b) |
| 4 | (n,inelastic) | ( E-thr = 944.8 keV ) | 380.7 (mb) | 994.9 (mb) | |||
| 16 | (n,2n) | ( E-thr = 8.730 MeV ) | 1.324 (b) | 1.601 (mb) | |||
| 17 | (n,3n) | ( E-thr = 16.01 MeV ) | − | 321.0 (nb) | |||
| 22 | (n,na) | ( E-thr = 3.000 MeV ) | 1.561 (mb) | 350.9 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.503 MeV ) | 676.1 (μb) | 196.8 (nb) | |||
| 32 | (n,nd) | ( E-thr = 15.20 MeV ) | − | 35.63e-12 (b) | |||
| 33 | (n,nt) | ( E-thr = 15.88 MeV ) | − | 1.031e-12 (b) | |||
| 102 | (n,γ) | 229.2 (mb) | 229.2 (mb) | 1.000 | 713.2 (mb) | 1.020 (mb) | 19.32 (mb) |
| 103 | (n,p) | ( E-thr = 2.883 MeV ) | 19.58 (mb) | 21.02 (μb) | |||
| 104 | (n,d) | ( E-thr = 7.168 MeV ) | 692.2 (μb) | 180.7 (nb) | |||
| 105 | (n,t) | ( E-thr = 8.947 MeV ) | 27.46 (μb) | 16.57 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 983.5 (μb) | 9.217 (mb) | 55.62 (μb) |
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These cross sections are calculated from JENDL-3.2 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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