| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 292.0 (b) | 300.1 (b) | 1.028 | − | 5.951 (b) | 7.893 (b) |
| 2 | (n,elastic) | 2.667 (b) | 2.828 (b) | 1.060 | − | 2.655 (b) | 4.724 (b) |
| 4 | (n,inelastic) | ( E-thr = 43.00 keV ) | 440.3 (mb) | 1.754 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.562 MeV ) | 615.6 (mb) | 3.705 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.23 MeV ) | 24.61 (mb) | 3.852 (μb) | |||
| 18 | (n,fission) | 36.21 (mb) | 37.84 (mb) | 1.045 | 8.130 (b) | 2.208 (b) | 1.328 (b) |
| 19 | (n,f) | 36.21 (mb) | 37.84 (mb) | 1.045 | 7.642 (b) | 840.8 (mb) | 1.304 (b) |
| 20 | (n,nf) | ( E-thr = 1.300 MeV ) | 1.264 (b) | 23.82 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 8.000 MeV ) | 103.3 (mb) | 15.93 (μb) | |||
| 38 | (n,3nf) | ( E-thr = 14.00 MeV ) | 0.000 (b) | 4.768 (nb) | |||
| 102 | (n,γ) | 289.3 (b) | 297.2 (b) | 1.027 | 8.502 (kb) | 1.093 (mb) | 81.54 (mb) |
| 456 | νp | 2.825 | − | − | − | 4.905 | − |
| 455 | νd | 9.110e-3 | − | − | − | 7.380e-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.
|