| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 4.111 (b) | 4.644 (b) | 1.130 | − | 4.638 (b) | 5.522 (b) |
| 2 | (n,elastic) | 4.017 (b) | 4.532 (b) | 1.128 | − | 2.930 (b) | 4.773 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.150 MeV ) | 178.7 (mb) | 740.7 (mb) | |||
| 16 | (n,2n) | ( E-thr = 8.264 MeV ) | 1.529 (b) | 3.124 (mb) | |||
| 17 | (n,3n) | ( E-thr = 14.05 MeV ) | − | 7.990 (μb) | |||
| 22 | (n,na) | ( E-thr = 7.758 MeV ) | 319.9e-15 (b) | 10.58e-12 (b) | |||
| 28 | (n,np) | ( E-thr = 12.92 MeV ) | 0.000 (b) | 140.3e-12 (b) | |||
| 102 | (n,γ) | 90.03 (mb) | 90.04 (mb) | 1.000 | 149.1 (mb) | 1.000 (mb) | 4.385 (mb) |
| 103 | (n,p) | ( E-thr = 7.400 MeV ) | 46.82 (μb) | 16.63 (nb) | |||
| 104 | (n,d) | ( E-thr = 10.59 MeV ) | 33.98e-18 (b) | 450.6e-12 (b) | |||
| 105 | (n,t) | ( E-thr = 11.89 MeV ) | 67.84e-21 (b) | 183.8e-12 (b) | |||
| 107 | (n,a) | ( E-thr = 2.809 MeV ) | 147.1 (nb) | 442.3e-12 (b) | |||
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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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