| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 2.213 (kb) | 2.218 (kb) | 1.002 | − | 5.605 (b) | 7.746 (b) |
| 2 | (n,elastic) | 11.22 (b) | 12.67 (b) | 1.129 | − | 2.522 (b) | 4.335 (b) |
| 4 | (n,inelastic) | 4.802 (μb) | 4.801 (μb) | 1.000 | 7.744 (b) | 444.8 (mb) | 2.153 (b) |
| 16 | (n,2n) | ( E-thr = 5.302 MeV ) | 478.3 (mb) | 18.55 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.69 MeV ) | 32.21 (mb) | 6.377 (μb) | |||
| 18 | (n,fission) | 1.601 (kb) | 1.602 (kb) | 1.001 | 668.4 (b) | 2.126 (b) | 1.178 (b) |
| 19 | (n,f) | 1.601 (kb) | 1.602 (kb) | 1.001 | 668.2 (b) | 1.026 (b) | 1.170 (b) |
| 20 | (n,nf) | ( E-thr = 2.300 MeV ) | 818.2 (mb) | 8.179 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.500 MeV ) | 282.4 (mb) | 44.70 (μb) | |||
| 37 | (n,4n) | ( E-thr = 17.25 MeV ) | − | 1.508 (nb) | |||
| 38 | (n,3nf) | ( E-thr = 15.00 MeV ) | − | 517.5e-12 (b) | |||
| 102 | (n,γ) | 600.2 (b) | 600.4 (b) | 1.000 | 253.6 (b) | 1.052 (mb) | 59.07 (mb) |
| 456 | νp | 3.138 | − | − | − | 5.714 | − |
| 455 | νd | 1.380e-2 | − | − | − | 9.460e-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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