| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 16.93 (b) | 18.04 (b) | 1.065 | − | 5.884 (b) | 7.758 (b) |
| 2 | (n,elastic) | 9.342 (b) | 10.54 (b) | 1.129 | − | 2.789 (b) | 4.825 (b) |
| 4 | (n,inelastic) | ( E-thr = 77.33 eV ) | 577.0 (mb) | 2.536 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.320 MeV ) | 971.3 (mb) | 14.07 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.33 MeV ) | 403.1 (mb) | 58.07 (μb) | |||
| 18 | (n,fission) | 4.213 (b) | 4.114 (b) | 0.977 | 3.208 (b) | 1.143 (b) | 313.0 (mb) |
| 19 | (n,f) | 4.213 (b) | 4.114 (b) | 0.977 | 2.961 (b) | 412.0 (mb) | 301.1 (mb) |
| 20 | (n,nf) | ( E-thr = 3.500 MeV ) | 587.9 (mb) | 11.95 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.500 MeV ) | 142.8 (mb) | 18.68 (μb) | |||
| 37 | (n,4n) | ( E-thr = 17.90 MeV ) | − | 2.019 (nb) | |||
| 38 | (n,3nf) | ( E-thr = 14.50 MeV ) | − | 36.48 (nb) | |||
| 102 | (n,γ) | 3.380 (b) | 3.381 (b) | 1.000 | 274.6 (b) | 591.6 (μb) | 70.28 (mb) |
|
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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