| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 15.60 (b) | 15.88 (b) | 1.018 | − | 2.567 (b) | 3.671 (b) |
| 2 | (n,elastic) | 2.187 (b) | 2.468 (b) | 1.128 | − | 1.214 (b) | 2.783 (b) |
| 4 | (n,inelastic) | ( E-thr = 128.3 keV ) | 525.7 (mb) | 884.6 (mb) | |||
| 16 | (n,2n) | ( E-thr = 10.41 MeV ) | 719.0 (mb) | 211.6 (μb) | |||
| 22 | (n,na) | ( E-thr = 8.082 MeV ) | 1.007 (mb) | 502.7 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.216 MeV ) | 36.58 (mb) | 11.39 (μb) | |||
| 102 | (n,γ) | 13.42 (b) | 13.42 (b) | 1.000 | 11.76 (b) | 665.0 (μb) | 2.898 (mb) |
| 103 | (n,p) | ( E-thr = 1.855 MeV ) | 37.40 (mb) | 578.1 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.951 MeV ) | 4.400 (mb) | 4.928 (μb) | |||
| 105 | (n,t) | ( E-thr = 9.476 MeV ) | 870.0 (μb) | 135.7 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 12.94 MeV ) | 0.000 (b) | 5.933 (nb) | |||
| 107 | (n,a) | ( E-thr = 635.8 keV ) | 27.69 (mb) | 126.8 (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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