| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 5.244 (b) | 5.892 (b) | 1.123 | − | 4.399 (b) | 5.858 (b) |
| 2 | (n,elastic) | 5.019 (b) | 5.666 (b) | 1.129 | − | 2.341 (b) | 4.161 (b) |
| 4 | (n,inelastic) | ( E-thr = 105.0 keV ) | 453.2 (mb) | 1.658 (b) | |||
| 16 | (n,2n) | ( E-thr = 8.895 MeV ) | 1.601 (b) | 2.064 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.10 MeV ) | − | 1.389 (μb) | |||
| 22 | (n,na) | ( E-thr = 4.493 MeV ) | 23.39 (μb) | 19.01 (nb) | |||
| 28 | (n,np) | ( E-thr = 10.72 MeV ) | 2.687 (μb) | 17.27 (nb) | |||
| 102 | (n,γ) | 225.6 (mb) | 225.5 (mb) | 0.999 | 3.284 (b) | 3.179 (mb) | 33.97 (mb) |
| 103 | (n,p) | ( E-thr = 4.835 MeV ) | 2.818 (mb) | 700.3 (nb) | |||
| 104 | (n,d) | ( E-thr = 8.480 MeV ) | 61.29 (μb) | 28.44 (nb) | |||
| 105 | (n,t) | ( E-thr = 10.30 MeV ) | 9.963 (nb) | 336.3e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 11.64 MeV ) | 180.9e-27 (b) | 9.305e-18 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 2.925 (μb) | 1.204 (mb) | 365.7 (nb) |
|
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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