| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 2.261 (kb) | 2.264 (kb) | 1.002 | − | 6.001 (b) | 8.422 (b) |
| 2 | (n,elastic) | 9.419 (b) | 10.64 (b) | 1.129 | − | 2.795 (b) | 4.437 (b) |
| 4 | (n,inelastic) | 300.1 (μb) | 300.2 (μb) | 1.000 | 6.850 (b) | 343.0 (mb) | 1.997 (b) |
| 16 | (n,2n) | ( E-thr = 5.029 MeV ) | 403.5 (mb) | 27.00 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.41 MeV ) | 76.46 (mb) | 11.09 (μb) | |||
| 18 | (n,fission) | 2.001 (kb) | 2.001 (kb) | 1.000 | 1.426 (kb) | 2.377 (b) | 1.913 (b) |
| 19 | (n,f) | 2.001 (kb) | 2.001 (kb) | 1.000 | 1.426 (kb) | 1.340 (b) | 1.905 (b) |
| 20 | (n,nf) | ( E-thr = 2.300 MeV ) | 729.1 (mb) | 8.095 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.000 MeV ) | 309.1 (mb) | 67.23 (μb) | |||
| 37 | (n,4n) | ( E-thr = 16.72 MeV ) | − | 12.20 (nb) | |||
| 38 | (n,3nf) | ( E-thr = 14.00 MeV ) | 0.000 (b) | 3.680 (nb) | |||
| 102 | (n,γ) | 250.1 (b) | 250.5 (b) | 1.001 | 178.3 (b) | 822.2 (μb) | 44.04 (mb) |
| 456 | νp | 4.077 | − | − | − | 7.493 | − |
| 455 | νd | 5.999e-3 | − | − | − | 4.107e-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.
|