| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 3.189 (kb) | 3.165 (kb) | 0.992 | − | 5.203 (b) | 6.626 (b) |
| 2 | (n,elastic) | 109.8 (b) | 121.9 (b) | 1.110 | − | 2.743 (b) | 5.126 (b) |
| 4 | (n,inelastic) | ( E-thr = 428.2 keV ) | 505.5 (mb) | 1.493 (b) | |||
| 16 | (n,2n) | ( E-thr = 8.794 MeV ) | 1.949 (b) | 2.017 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.89 MeV ) | − | 579.2 (nb) | |||
| 22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 103.9 (nb) | 27.13 (μb) | 14.70 (nb) |
| 28 | (n,np) | ( E-thr = 6.603 MeV ) | 99.38 (μb) | 46.23 (nb) | |||
| 102 | (n,γ) | 3.079 (kb) | 3.043 (kb) | 0.988 | 420.2 (b) | 14.52 (nb) | 6.105 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 89.97 (μb) | 6.003 (mb) | 4.821 (μb) |
| 104 | (n,d) | ( E-thr = 4.367 MeV ) | 526.0 (μb) | 136.6 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 15.76 (μb) | 577.4 (μb) | 1.822 (μb) |
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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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