| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 5.343 (b) | 5.772 (b) | 1.080 | − | 4.480 (b) | 5.580 (b) |
| 2 | (n,elastic) | 3.334 (b) | 3.762 (b) | 1.128 | − | 2.657 (b) | 3.897 (b) |
| 4 | (n,inelastic) | ( E-thr = 116.8 keV ) | 183.6 (mb) | 1.547 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.596 MeV ) | 1.621 (b) | 10.78 (mb) | |||
| 17 | (n,3n) | ( E-thr = 16.25 MeV ) | − | 912.4 (nb) | |||
| 22 | (n,na) | ( E-thr = 3.565 MeV ) | 68.51 (μb) | 21.22 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.380 MeV ) | 94.77 (μb) | 52.96 (nb) | |||
| 32 | (n,nd) | ( E-thr = 13.70 MeV ) | 0.000 (b) | 224.5e-12 (b) | |||
| 102 | (n,γ) | 2.008 (b) | 2.010 (b) | 1.001 | 112.2 (b) | 1.002 (mb) | 121.5 (mb) |
| 103 | (n,p) | ( E-thr = 735.4 keV ) | 13.68 (mb) | 13.13 (μb) | |||
| 104 | (n,d) | ( E-thr = 7.048 MeV ) | 458.9 (μb) | 108.5 (nb) | |||
| 105 | (n,t) | ( E-thr = 7.460 MeV ) | 9.925 (μb) | 9.258 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 79.69 (μb) | 3.091 (mb) | 8.855 (μb) |
|
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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