| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 23.79 (b) | 25.02 (b) | 1.052 | − | 2.869 (b) | 3.779 (b) |
| 2 | (n,elastic) | 9.583 (b) | 10.81 (b) | 1.128 | − | 1.503 (b) | 3.299 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.192 MeV ) | 484.9 (mb) | 476.0 (mb) | |||
| 16 | (n,2n) | ( E-thr = 10.78 MeV ) | 836.3 (mb) | 196.9 (μb) | |||
| 22 | (n,na) | ( E-thr = 7.130 MeV ) | 1.252 (mb) | 454.6 (nb) | |||
| 28 | (n,np) | ( E-thr = 11.32 MeV ) | 477.1 (μb) | 447.6 (nb) | |||
| 102 | (n,γ) | 14.20 (b) | 14.20 (b) | 1.000 | 6.888 (b) | 28.94 (μb) | 3.450 (mb) |
| 103 | (n,p) | ( E-thr = 4.532 MeV ) | 27.96 (mb) | 37.58 (μb) | |||
| 104 | (n,d) | ( E-thr = 8.976 MeV ) | 169.4 (μb) | 59.32 (nb) | |||
| 105 | (n,t) | ( E-thr = 12.17 MeV ) | 5.744 (nb) | 3.780 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 12.36 MeV ) | 1.474e-21 (b) | 201.1e-15 (b) | |||
| 107 | (n,a) | ( E-thr = 436.8 keV ) | 15.20 (mb) | 45.28 (μb) | |||
| 111 | (n,2p) | ( E-thr = 14.48 MeV ) | − | 65.83e-15 (b) | |||
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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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