| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 12.34 (b) | 13.18 (b) | 1.068 | − | 4.537 (b) | 5.613 (b) |
| 2 | (n,elastic) | 6.498 (b) | 7.336 (b) | 1.129 | − | 2.567 (b) | 4.387 (b) |
| 4 | (n,inelastic) | ( E-thr = 545.0 keV ) | 471.0 (mb) | 1.166 (b) | |||
| 16 | (n,2n) | ( E-thr = 9.776 MeV ) | 1.472 (b) | 871.4 (μb) | |||
| 17 | (n,3n) | ( E-thr = 17.32 MeV ) | − | 266.5 (nb) | |||
| 22 | (n,na) | ( E-thr = 2.877 MeV ) | 2.303 (mb) | 594.3 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.282 MeV ) | 1.159 (mb) | 285.5 (nb) | |||
| 32 | (n,nd) | ( E-thr = 16.01 MeV ) | − | 1.065e-12 (b) | |||
| 102 | (n,γ) | 5.842 (b) | 5.845 (b) | 1.000 | 11.51 (b) | 1.053 (mb) | 55.93 (mb) |
| 103 | (n,p) | ( E-thr = 2.445 MeV ) | 13.88 (mb) | 18.43 (μb) | |||
| 104 | (n,d) | ( E-thr = 6.948 MeV ) | 120.0 (μb) | 48.43 (nb) | |||
| 105 | (n,t) | ( E-thr = 9.760 MeV ) | 941.9 (nb) | 4.826 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 1.140 (mb) | 8.501 (mb) | 69.80 (μb) |
|
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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