| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 36.41 (b) | 37.93 (b) | 1.042 | − | 5.905 (b) | 7.913 (b) |
| 2 | (n,elastic) | 12.61 (b) | 14.22 (b) | 1.128 | − | 2.401 (b) | 4.641 (b) |
| 4 | (n,inelastic) | ( E-thr = 42.31 keV ) | 359.0 (mb) | 1.321 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.999 MeV ) | 231.1 (mb) | 920.7 (μb) | |||
| 17 | (n,3n) | ( E-thr = 13.12 MeV ) | 119.6 (μb) | 85.38 (nb) | |||
| 18 | (n,fission) | 4.665 (b) | 4.646 (b) | 0.996 | 19.32 (b) | 2.907 (b) | 1.775 (b) |
| 19 | (n,f) | 4.665 (b) | 4.646 (b) | 0.996 | 18.87 (b) | 1.416 (b) | 1.753 (b) |
| 20 | (n,nf) | ( E-thr = 2.300 MeV ) | 1.471 (b) | 21.72 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 9.500 MeV ) | 19.89 (mb) | 5.059 (μb) | |||
| 38 | (n,3nf) | ( E-thr = 16.00 MeV ) | − | 45.01e-12 (b) | |||
| 102 | (n,γ) | 19.13 (b) | 19.06 (b) | 0.996 | 132.6 (b) | 1.186 (mb) | 172.0 (mb) |
| 456 | νp | 3.452 | − | − | − | 5.546 | − |
| 455 | νd | 2.114e-3 | − | − | − | 1.771e-3 | − |
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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.
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