| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 3.857 (b) | 4.337 (b) | 1.124 | − | 4.746 (b) | 5.795 (b) |
| 2 | (n,elastic) | 3.717 (b) | 4.197 (b) | 1.129 | − | 2.746 (b) | 4.925 (b) |
| 4 | (n,inelastic) | ( E-thr = 105.0 keV ) | 320.9 (mb) | 853.1 (mb) | |||
| 16 | (n,2n) | ( E-thr = 8.886 MeV ) | 1.680 (b) | 2.029 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.11 MeV ) | − | 926.4 (nb) | |||
| 22 | (n,na) | ( E-thr = 5.709 MeV ) | 83.92 (nb) | 614.6e-12 (b) | |||
| 28 | (n,np) | ( E-thr = 11.49 MeV ) | 8.268 (nb) | 2.422 (nb) | |||
| 102 | (n,γ) | 139.6 (mb) | 139.4 (mb) | 0.998 | 954.4 (mb) | 764.5 (μb) | 12.60 (mb) |
| 103 | (n,p) | ( E-thr = 5.632 MeV ) | 664.8 (μb) | 149.9 (nb) | |||
| 104 | (n,d) | ( E-thr = 9.245 MeV ) | 4.010 (μb) | 7.830 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.18 MeV ) | 7.067e-12 (b) | 55.21e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 12.94 MeV ) | 434.4e-33 (b) | 11.43e-21 (b) | |||
| 107 | (n,a) | ( E-thr = 395.3 keV ) | 144.1 (μb) | 37.24 (nb) | |||
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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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