| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 11.98 (b) | 13.19 (b) | 1.100 | − | 5.884 (b) | 7.759 (b) |
| 2 | (n,elastic) | 9.300 (b) | 10.50 (b) | 1.129 | − | 2.789 (b) | 4.827 (b) |
| 4 | (n,inelastic) | ( E-thr = 45.11 keV ) | 578.1 (mb) | 2.541 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.180 MeV ) | 974.4 (mb) | 14.08 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.33 MeV ) | 405.8 (mb) | 58.45 (μb) | |||
| 18 | (n,fission) | 16.80 (μb) | 16.83 (μb) | 1.002 | 1.241 (b) | 1.136 (b) | 306.4 (mb) |
| 19 | (n,f) | 16.80 (μb) | 16.83 (μb) | 1.002 | 994.5 (mb) | 409.3 (mb) | 294.5 (mb) |
| 20 | (n,nf) | ( E-thr = 4.000 MeV ) | 586.6 (mb) | 11.92 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 10.00 MeV ) | 140.1 (mb) | 18.14 (μb) | |||
| 37 | (n,4n) | ( E-thr = 17.90 MeV ) | − | 2.032 (nb) | |||
| 38 | (n,3nf) | ( E-thr = 15.50 MeV ) | − | 36.70 (nb) | |||
| 102 | (n,γ) | 2.683 (b) | 2.690 (b) | 1.003 | 275.6 (b) | 589.4 (μb) | 70.16 (mb) |
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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 :
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