| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 3.751 (b) | 4.233 (b) | 1.128 | − | 1.741 (b) | 3.610 (b) |
| 2 | (n,elastic) | 3.742 (b) | 4.223 (b) | 1.129 | − | 1.046 (b) | 2.324 (b) |
| 4 | (n,inelastic) | ( E-thr = 115.8 keV ) | 164.2 (mb) | 1.265 (b) | |||
| 16 | (n,2n) | ( E-thr = 10.99 MeV ) | 42.94 (mb) | 8.615 (μb) | |||
| 22 | (n,na) | ( E-thr = 4.226 MeV ) | 359.4 (mb) | 4.614 (mb) | |||
| 28 | (n,np) | ( E-thr = 8.417 MeV ) | 42.81 (mb) | 13.20 (μb) | |||
| 32 | (n,nd) | ( E-thr = 14.55 MeV ) | − | 31.83 (nb) | |||
| 102 | (n,γ) | 9.570 (mb) | 9.576 (mb) | 1.001 | 19.47 (mb) | 25.67 (μb) | 211.7 (μb) |
| 103 | (n,p) | ( E-thr = 4.251 MeV ) | 14.66 (mb) | 1.163 (mb) | |||
| 104 | (n,d) | ( E-thr = 6.074 MeV ) | 34.08 (mb) | 75.92 (μb) | |||
| 105 | (n,t) | ( E-thr = 7.959 MeV ) | 15.30 (mb) | 30.23 (μb) | |||
| 107 | (n,a) | ( E-thr = 1.603 MeV ) | 21.34 (mb) | 14.65 (mb) | |||
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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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