| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 1.771 (kb) | 1.779 (kb) | 1.004 | − | 5.974 (b) | 8.393 (b) |
| 2 | (n,elastic) | 9.720 (b) | 10.98 (b) | 1.129 | − | 2.801 (b) | 4.544 (b) |
| 4 | (n,inelastic) | ( E-thr = 34.61 keV ) | 337.0 (mb) | 2.744 (b) | |||
| 16 | (n,2n) | ( E-thr = 4.990 MeV ) | 423.2 (mb) | 36.12 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.32 MeV ) | 73.00 (mb) | 10.19 (μb) | |||
| 18 | (n,fission) | 980.6 (b) | 982.7 (b) | 1.002 | 623.5 (b) | 2.334 (b) | 1.013 (b) |
| 19 | (n,f) | 980.6 (b) | 982.7 (b) | 1.002 | 623.2 (b) | 1.075 (b) | 1.004 (b) |
| 20 | (n,nf) | ( E-thr = 2.300 MeV ) | 864.8 (mb) | 9.563 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.000 MeV ) | 395.0 (mb) | 86.64 (μb) | |||
| 37 | (n,4n) | ( E-thr = 16.82 MeV ) | − | 4.051 (nb) | |||
| 38 | (n,3nf) | ( E-thr = 13.50 MeV ) | 25.56e-21 (b) | 8.352 (nb) | |||
| 102 | (n,γ) | 780.5 (b) | 782.7 (b) | 1.003 | 491.9 (b) | 873.4 (μb) | 53.40 (mb) |
| 456 | νp | 3.559 | − | − | − | 6.639 | − |
| 455 | νd | 1.300e-2 | − | − | − | 8.900e-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.
|