| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 699.2 (b) | 707.5 (b) | 1.012 | − | 5.583 (b) | 7.651 (b) |
| 2 | (n,elastic) | 11.82 (b) | 12.83 (b) | 1.085 | − | 2.269 (b) | 4.663 (b) |
| 4 | (n,inelastic) | ( E-thr = 41.35 keV ) | 341.5 (mb) | 1.351 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.675 MeV ) | 260.9 (mb) | 1.155 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.65 MeV ) | 395.6 (μb) | 122.9 (nb) | |||
| 18 | (n,fission) | 3.122 (b) | 3.191 (b) | 1.022 | 13.28 (b) | 2.710 (b) | 1.395 (b) |
| 19 | (n,f) | 3.122 (b) | 3.191 (b) | 1.022 | 12.93 (b) | 1.653 (b) | 1.378 (b) |
| 20 | (n,nf) | ( E-thr = 4.000 MeV ) | 1.006 (b) | 16.62 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 11.00 MeV ) | 50.94 (mb) | 7.195 (μb) | |||
| 38 | (n,3nf) | ( E-thr = 17.50 MeV ) | − | 50.04e-12 (b) | |||
| 102 | (n,γ) | 684.3 (b) | 691.4 (b) | 1.010 | 1.588 (kb) | 1.240 (mb) | 238.6 (mb) |
| 456 | νp | 3.111 | − | − | − | 5.141 | − |
| 455 | νd | 4.900e-3 | − | − | − | 3.567e-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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