| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 1.387 (kb) | 1.446 (kb) | 1.043 | − | 5.999 (b) | 8.009 (b) |
| 2 | (n,elastic) | 11.26 (b) | 12.48 (b) | 1.108 | − | 2.670 (b) | 4.543 (b) |
| 4 | (n,inelastic) | ( E-thr = 42.15 keV ) | 382.3 (mb) | 1.752 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.263 MeV ) | 603.4 (mb) | 13.69 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.82 MeV ) | 78.67 (mb) | 11.08 (μb) | |||
| 18 | (n,fission) | 1.012 (kb) | 1.060 (kb) | 1.047 | 567.4 (b) | 2.260 (b) | 1.626 (b) |
| 19 | (n,f) | 1.012 (kb) | 1.060 (kb) | 1.047 | 566.9 (b) | 730.9 (mb) | 1.606 (b) |
| 20 | (n,nf) | ( E-thr = 1.600 MeV ) | 1.142 (b) | 20.15 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 6.500 MeV ) | 386.9 (mb) | 66.71 (μb) | |||
| 37 | (n,4n) | ( E-thr = 17.49 MeV ) | − | 1.480 (nb) | |||
| 38 | (n,3nf) | ( E-thr = 13.50 MeV ) | 20.27e-18 (b) | 4.927 (nb) | |||
| 102 | (n,γ) | 363.1 (b) | 373.7 (b) | 1.029 | 180.4 (b) | 920.7 (μb) | 71.97 (mb) |
| 456 | νp | 2.931 | − | − | − | 5.027 | − |
| 455 | νd | 1.600e-2 | − | − | − | 9.854e-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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