| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 212.3 (b) | 216.7 (b) | 1.021 | − | 5.823 (b) | 7.624 (b) |
| 2 | (n,elastic) | 10.59 (b) | 11.80 (b) | 1.114 | − | 2.788 (b) | 4.412 (b) |
| 4 | (n,inelastic) | ( E-thr = 9.246 keV ) | 353.2 (mb) | 2.170 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.850 MeV ) | 1.283 (b) | 3.434 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.67 MeV ) | 20.56 (mb) | 6.255 (μb) | |||
| 18 | (n,fission) | 23.65 (mb) | 23.15 (mb) | 0.979 | 3.240 (b) | 1.377 (b) | 849.8 (mb) |
| 19 | (n,f) | 23.65 (mb) | 23.15 (mb) | 0.979 | 2.728 (b) | 558.2 (mb) | 827.5 (mb) |
| 20 | (n,nf) | ( E-thr = 2.000 MeV ) | 794.4 (mb) | 22.26 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 10.00 MeV ) | 24.54 (mb) | 9.776 (μb) | |||
| 38 | (n,3nf) | ( E-thr = 15.00 MeV ) | − | 628.8e-12 (b) | |||
| 102 | (n,γ) | 201.7 (b) | 204.9 (b) | 1.016 | 541.8 (b) | 1.190 (mb) | 186.8 (mb) |
| 456 | νp | 2.086 | − | − | − | 3.973 | − |
| 455 | νd | 1.083e-2 | − | − | − | 8.785e-3 | − |
|
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 :
νp,
νd
: numbers of prompt and delayed neutrons per fission.
|