| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 7.743 (b) | 8.675 (b) | 1.120 | − | 3.377 (b) | 4.163 (b) |
| 2 | (n,elastic) | 7.224 (b) | 8.155 (b) | 1.129 | − | 1.819 (b) | 3.044 (b) |
| 4 | (n,inelastic) | 0.000 (b) | 0.000 (b) | − | 3.815 (b) | 518.1 (mb) | 1.112 (b) |
| 16 | (n,2n) | ( E-thr = 10.34 MeV ) | 1.026 (b) | 351.7 (μb) | |||
| 17 | (n,3n) | ( E-thr = 17.21 MeV ) | − | 25.62 (nb) | |||
| 22 | (n,na) | ( E-thr = 6.373 MeV ) | 250.6 (μb) | 86.85 (nb) | |||
| 24 | (n,2na) | ( E-thr = 15.71 MeV ) | − | 203.3e-18 (b) | |||
| 28 | (n,np) | ( E-thr = 11.16 MeV ) | 304.0 (μb) | 113.6 (nb) | |||
| 102 | (n,γ) | 519.0 (mb) | 519.3 (mb) | 1.000 | 646.2 (mb) | 465.9 (μb) | 5.936 (mb) |
| 103 | (n,p) | ( E-thr = 4.649 MeV ) | 9.910 (mb) | 9.009 (μb) | |||
| 107 | (n,a) | ( E-thr = 460.2 keV ) | 3.770 (mb) | 5.644 (μb) | |||
| 112 | (n,pa) | ( E-thr = 12.27 MeV ) | 4.689e-15 (b) | 283.7e-18 (b) | |||
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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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