| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 2.100 (kb) | 2.142 (kb) | 1.020 | − | 5.868 (b) | 7.651 (b) |
| 2 | (n,elastic) | 23.91 (b) | 26.37 (b) | 1.103 | − | 2.808 (b) | 4.350 (b) |
| 4 | (n,inelastic) | ( E-thr = 60.26 keV ) | 316.1 (mb) | 2.250 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.573 MeV ) | 1.016 (b) | 20.77 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.42 MeV ) | 12.03 (mb) | 6.177 (μb) | |||
| 18 | (n,fission) | 1.487 (kb) | 1.536 (kb) | 1.032 | 931.1 (b) | 1.714 (b) | 972.5 (mb) |
| 19 | (n,f) | 1.487 (kb) | 1.536 (kb) | 1.032 | 930.9 (b) | 641.0 (mb) | 964.1 (mb) |
| 20 | (n,nf) | ( E-thr = 3.000 MeV ) | 673.1 (mb) | 8.366 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.500 MeV ) | 400.8 (mb) | 55.63 (μb) | |||
| 37 | (n,4n) | ( E-thr = 18.24 MeV ) | − | 131.9e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 16.00 MeV ) | − | 174.5e-12 (b) | |||
| 102 | (n,γ) | 589.0 (b) | 580.3 (b) | 0.985 | 165.4 (b) | 1.021 (mb) | 55.27 (mb) |
| 456 | νp | 2.086 | − | − | − | 4.000 | − |
| 455 | νd | 1.577e-2 | − | − | − | 1.189e-2 | − |
|
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.
|