| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 10.44 (b) | 10.69 (b) | 1.024 | − | 4.480 (b) | 5.579 (b) |
| 2 | (n,elastic) | 1.930 (b) | 2.176 (b) | 1.128 | − | 2.364 (b) | 4.219 (b) |
| 4 | (n,inelastic) | ( E-thr = 438.1 keV ) | 467.3 (mb) | 1.302 (b) | |||
| 16 | (n,2n) | ( E-thr = 9.314 MeV ) | 1.637 (b) | 1.348 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.91 MeV ) | − | 1.795 (μb) | |||
| 22 | (n,na) | ( E-thr = 3.882 MeV ) | 71.64 (μb) | 23.06 (nb) | |||
| 28 | (n,np) | ( E-thr = 10.05 MeV ) | 21.48 (μb) | 20.34 (nb) | |||
| 102 | (n,γ) | 8.507 (b) | 8.515 (b) | 1.001 | 252.1 (b) | 1.097 (mb) | 54.28 (mb) |
| 103 | (n,p) | ( E-thr = 3.755 MeV ) | 9.123 (mb) | 4.314 (μb) | |||
| 104 | (n,d) | ( E-thr = 7.718 MeV ) | 16.18 (μb) | 18.53 (nb) | |||
| 105 | (n,t) | ( E-thr = 10.12 MeV ) | 81.58 (nb) | 1.835 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 27.70 (μb) | 2.045 (mb) | 1.492 (μb) |
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These cross sections are calculated from JENDL-3.2 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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