| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 23.98 (b) | 24.97 (b) | 1.041 | − | 3.750 (b) | 5.154 (b) |
| 2 | (n,elastic) | 6.938 (b) | 7.830 (b) | 1.129 | − | 2.013 (b) | 4.450 (b) |
| 4 | (n,inelastic) | ( E-thr = 393.0 keV ) | 575.1 (mb) | 688.3 (mb) | |||
| 16 | (n,2n) | ( E-thr = 8.526 MeV ) | 1.121 (b) | 613.0 (μb) | |||
| 22 | (n,na) | ( E-thr = 7.409 MeV ) | 157.3 (nb) | 2.263 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.532 MeV ) | 800.9 (μb) | 263.9 (nb) | |||
| 32 | (n,nd) | ( E-thr = 16.03 MeV ) | − | 1.290e-12 (b) | |||
| 102 | (n,γ) | 17.04 (b) | 17.14 (b) | 1.006 | 121.4 (b) | 923.6 (μb) | 14.00 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 3.958 (mb) | 37.01 (mb) | 442.9 (μb) |
| 104 | (n,d) | ( E-thr = 7.281 MeV ) | 960.3 (μb) | 174.4 (nb) | |||
| 105 | (n,t) | ( E-thr = 9.703 MeV ) | 42.10 (nb) | 861.4e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 10.38 MeV ) | 0.000 (b) | 215.9e-15 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 48.47 (μb) | 1.143 (mb) | 2.756 (μb) |
|
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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