| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 5.468 (b) | 6.170 (b) | 1.128 | − | 4.335 (b) | 5.589 (b) |
| 2 | (n,elastic) | 5.463 (b) | 6.164 (b) | 1.128 | − | 2.827 (b) | 5.176 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.857 MeV ) | 610.8 (mb) | 408.3 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.25 MeV ) | 881.2 (mb) | 171.9 (μb) | |||
| 17 | (n,3n) | ( E-thr = 19.78 MeV ) | − | 1.865e-12 (b) | |||
| 22 | (n,na) | ( E-thr = 7.991 MeV ) | 210.5 (nb) | 3.518 (nb) | |||
| 28 | (n,np) | ( E-thr = 10.73 MeV ) | 64.64 (μb) | 78.91 (nb) | |||
| 102 | (n,γ) | 5.802 (mb) | 5.802 (mb) | 1.000 | 62.65 (mb) | 1.004 (mb) | 2.357 (mb) |
| 103 | (n,p) | ( E-thr = 4.578 MeV ) | 12.21 (mb) | 4.941 (μb) | |||
| 104 | (n,d) | ( E-thr = 8.394 MeV ) | 72.35 (μb) | 45.97 (nb) | |||
| 105 | (n,t) | ( E-thr = 12.19 MeV ) | 4.607e-12 (b) | 1.060 (nb) | |||
| 107 | (n,a) | ( E-thr = 793.6 keV ) | 3.282 (mb) | 1.079 (μb) | |||
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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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