| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 12.51 (b) | 12.82 (b) | 1.025 | − | 5.215 (b) | 6.821 (b) |
| 2 | (n,elastic) | 2.388 (b) | 2.693 (b) | 1.128 | − | 2.596 (b) | 3.914 (b) |
| 4 | (n,inelastic) | ( E-thr = 46.76 keV ) | 484.7 (mb) | 2.842 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.225 MeV ) | 2.127 (b) | 14.67 (mb) | |||
| 17 | (n,3n) | ( E-thr = 14.32 MeV ) | − | 6.158 (μb) | |||
| 22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 525.3 (nb) | 57.97 (μb) | 35.64 (nb) |
| 28 | (n,np) | ( E-thr = 7.253 MeV ) | 48.35 (μb) | 34.20 (nb) | |||
| 102 | (n,γ) | 10.12 (b) | 10.13 (b) | 1.001 | 334.8 (b) | 1.000 (mb) | 49.24 (mb) |
| 103 | (n,p) | ( E-thr = 287.1 keV ) | 3.266 (mb) | 1.804 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.016 MeV ) | 709.1 (μb) | 154.8 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 83.69 (μb) | 1.906 (mb) | 5.950 (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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