| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 28.21 (b) | 29.47 (b) | 1.044 | − | 5.975 (b) | 7.983 (b) |
| 2 | (n,elastic) | 8.326 (b) | 9.373 (b) | 1.126 | − | 2.630 (b) | 4.717 (b) |
| 4 | (n,inelastic) | ( E-thr = 44.73 keV ) | 457.8 (mb) | 2.008 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.336 MeV ) | 741.9 (mb) | 6.390 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.60 MeV ) | 132.5 (mb) | 18.15 (μb) | |||
| 18 | (n,fission) | 2.436 (mb) | 2.454 (mb) | 1.007 | 4.359 (b) | 2.006 (b) | 1.151 (b) |
| 19 | (n,f) | 2.436 (mb) | 2.454 (mb) | 1.007 | 3.861 (b) | 774.2 (mb) | 1.125 (b) |
| 20 | (n,nf) | ( E-thr = 1.159 MeV ) | 1.075 (b) | 25.82 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 8.000 MeV ) | 157.2 (mb) | 22.02 (μb) | |||
| 37 | (n,4n) | ( E-thr = 18.16 MeV ) | − | 147.8e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 13.50 MeV ) | 974.8e-15 (b) | 9.526 (nb) | |||
| 102 | (n,γ) | 19.88 (b) | 20.09 (b) | 1.010 | 1.126 (kb) | 1.059 (mb) | 98.18 (mb) |
| 456 | νp | 2.878 | − | − | − | 4.804 | − |
| 455 | νd | 1.530e-2 | − | − | − | 1.230e-2 | − |
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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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