| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 9.019 (b) | 9.514 (b) | 1.055 | − | 5.078 (b) | 6.267 (b) |
| 2 | (n,elastic) | 3.896 (b) | 4.395 (b) | 1.128 | − | 2.909 (b) | 5.386 (b) |
| 4 | (n,inelastic) | ( E-thr = 281.3 keV ) | 462.1 (mb) | 855.9 (mb) | |||
| 16 | (n,2n) | ( E-thr = 6.954 MeV ) | 1.701 (b) | 7.103 (mb) | |||
| 17 | (n,3n) | ( E-thr = 16.13 MeV ) | − | 720.0 (nb) | |||
| 22 | (n,na) | ( E-thr = 2.511 MeV ) | 25.31 (μb) | 12.63 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.733 MeV ) | 21.63 (μb) | 34.90 (nb) | |||
| 32 | (n,nd) | ( E-thr = 13.22 MeV ) | 0.000 (b) | 199.8e-12 (b) | |||
| 102 | (n,γ) | 5.123 (b) | 5.119 (b) | 0.999 | 4.745 (b) | 1.000 (mb) | 14.73 (mb) |
| 103 | (n,p) | ( E-thr = 393.4 keV ) | 2.828 (mb) | 1.926 (μb) | |||
| 104 | (n,d) | ( E-thr = 6.405 MeV ) | 719.2 (μb) | 178.7 (nb) | |||
| 105 | (n,t) | ( E-thr = 6.994 MeV ) | 26.12 (μb) | 19.10 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 16.13 (μb) | 1.309 (mb) | 1.535 (μb) |
|
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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