| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 1.604 (kb) | 1.606 (kb) | 1.001 | − | 4.975 (b) | 5.882 (b) |
| 2 | (n,elastic) | 3.415 (b) | 3.854 (b) | 1.129 | − | 3.453 (b) | 4.710 (b) |
| 4 | (n,inelastic) | 0.000 (b) | 0.000 (b) | − | 3.336 (b) | 138.6 (mb) | 992.2 (mb) |
| 16 | (n,2n) | ( E-thr = 6.138 MeV ) | 1.378 (b) | 14.02 (mb) | |||
| 17 | (n,3n) | ( E-thr = 14.99 MeV ) | − | 2.981 (μb) | |||
| 22 | (n,na) | ( E-thr = 3.554 MeV ) | 2.073 (μb) | 2.769 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.646 MeV ) | 2.373 (nb) | 7.142 (nb) | |||
| 32 | (n,nd) | ( E-thr = 13.47 MeV ) | 0.000 (b) | 62.96e-12 (b) | |||
| 102 | (n,γ) | 1.601 (kb) | 1.601 (kb) | 1.001 | 754.5 (b) | 1.000 (mb) | 164.6 (mb) |
| 103 | (n,p) | ( E-thr = 1.607 MeV ) | 1.324 (mb) | 512.0 (nb) | |||
| 104 | (n,d) | ( E-thr = 7.317 MeV ) | 105.9 (μb) | 38.12 (nb) | |||
| 105 | (n,t) | ( E-thr = 7.234 MeV ) | 3.578 (μb) | 7.086 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 1.691 (μb) | 733.6 (μb) | 256.2 (nb) |
|
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 :
|