| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 7.912 (b) | 8.909 (b) | 1.126 | − | 3.366 (b) | 4.289 (b) |
| 2 | (n,elastic) | 7.762 (b) | 8.759 (b) | 1.128 | − | 1.791 (b) | 3.458 (b) |
| 4 | (n,inelastic) | ( E-thr = 570.4 keV ) | 470.3 (mb) | 826.3 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.567 MeV ) | 1.100 (b) | 662.2 (μb) | |||
| 17 | (n,3n) | ( E-thr = 16.14 MeV ) | − | 296.9 (nb) | |||
| 22 | (n,na) | ( E-thr = 7.605 MeV ) | 819.7 (nb) | 1.465 (nb) | |||
| 28 | (n,np) | ( E-thr = 12.12 MeV ) | 145.1 (nb) | 3.970 (nb) | |||
| 102 | (n,γ) | 150.1 (mb) | 150.0 (mb) | 1.000 | 1.322 (b) | 766.4 (μb) | 2.716 (mb) |
| 103 | (n,p) | ( E-thr = 5.926 MeV ) | 2.320 (mb) | 809.0 (nb) | |||
| 104 | (n,d) | ( E-thr = 9.865 MeV ) | 758.4 (μb) | 281.1 (nb) | |||
| 105 | (n,t) | ( E-thr = 12.33 MeV ) | 13.10e-12 (b) | 173.4e-12 (b) | |||
| 107 | (n,a) | ( E-thr = 2.428 MeV ) | 1.229 (mb) | 359.6 (nb) | |||
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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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