| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 26.13 (b) | 27.23 (b) | 1.042 | − | 2.458 (b) | 3.864 (b) |
| 2 | (n,elastic) | 8.538 (b) | 9.635 (b) | 1.128 | − | 1.206 (b) | 3.171 (b) |
| 4 | (n,inelastic) | ( E-thr = 574.7 keV ) | 456.1 (mb) | 689.3 (mb) | |||
| 16 | (n,2n) | ( E-thr = 8.092 MeV ) | 698.3 (mb) | 665.3 (μb) | |||
| 22 | (n,na) | ( E-thr = 9.326 MeV ) | 189.6 (μb) | 105.8 (nb) | |||
| 28 | (n,np) | ( E-thr = 11.34 MeV ) | 2.091 (mb) | 886.1 (nb) | |||
| 102 | (n,γ) | 17.59 (b) | 17.59 (b) | 1.000 | 8.358 (b) | 556.8 (μb) | 1.926 (mb) |
| 103 | (n,p) | ( E-thr = 2.691 MeV ) | 43.61 (mb) | 452.6 (μb) | |||
| 104 | (n,d) | ( E-thr = 9.078 MeV ) | 2.939 (mb) | 554.2 (nb) | |||
| 105 | (n,t) | ( E-thr = 10.15 MeV ) | 43.98 (μb) | 9.199 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 12.64 MeV ) | 50.78e-18 (b) | 6.225e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 7.214 (mb) | 48.39 (mb) | 570.0 (μb) |
| 111 | (n,2p) | ( E-thr = 12.56 MeV ) | 8.561e-18 (b) | 2.563e-12 (b) | |||
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These cross sections are calculated from JENDL-3.3 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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