| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 1.515 (b) | 1.520 (b) | 1.003 | − | 2.984 (b) | 3.938 (b) |
| 2 | (n,elastic) | 34.87 (mb) | 39.35 (mb) | 1.128 | − | 1.591 (b) | 3.511 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.367 MeV ) | 273.9 (mb) | 423.4 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.814 MeV ) | 1.109 (b) | 497.2 (μb) | |||
| 17 | (n,3n) | ( E-thr = 16.77 MeV ) | − | 183.3 (nb) | |||
| 22 | (n,na) | ( E-thr = 8.210 MeV ) | 35.95 (μb) | 44.72 (nb) | |||
| 28 | (n,np) | ( E-thr = 12.74 MeV ) | 6.134e-12 (b) | 27.57 (nb) | |||
| 102 | (n,γ) | 1.480 (b) | 1.480 (b) | 1.000 | 817.2 (mb) | 6.312 (μb) | 2.777 (mb) |
| 103 | (n,p) | ( E-thr = 6.627 MeV ) | 4.446 (mb) | 1.726 (μb) | |||
| 104 | (n,d) | ( E-thr = 10.39 MeV ) | 2.186 (μb) | 5.085 (nb) | |||
| 105 | (n,t) | ( E-thr = 12.67 MeV ) | 213.6e-15 (b) | 1.300 (nb) | |||
| 107 | (n,a) | ( E-thr = 2.472 MeV ) | 5.066 (mb) | 11.18 (μb) | |||
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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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