| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 645.5 (b) | 690.4 (b) | 1.069 | − | 5.516 (b) | 6.820 (b) |
| 2 | (n,elastic) | 1.335 (b) | 1.411 (b) | 1.057 | − | 2.722 (b) | 4.293 (b) |
| 4 | (n,inelastic) | ( E-thr = 79.80 keV ) | 387.9 (mb) | 2.425 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.474 MeV ) | 2.397 (b) | 13.27 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.00 MeV ) | − | 2.378 (μb) | |||
| 22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 102.9 (nb) | 22.82 (μb) | 10.79 (nb) |
| 28 | (n,np) | ( E-thr = 7.552 MeV ) | 40.64 (μb) | 29.52 (nb) | |||
| 32 | (n,nd) | ( E-thr = 11.60 MeV ) | 1.845e-12 (b) | 157.6e-12 (b) | |||
| 102 | (n,γ) | 644.2 (b) | 689.0 (b) | 1.069 | 3.000 (kb) | 1.978 (mb) | 89.71 (mb) |
| 103 | (n,p) | ( E-thr = 226.0 keV ) | 5.641 (mb) | 3.598 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.314 MeV ) | 516.1 (μb) | 110.4 (nb) | |||
| 105 | (n,t) | ( E-thr = 5.301 MeV ) | 25.93 (μb) | 6.757 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 63.32 (μb) | 1.697 (mb) | 4.194 (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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