| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 7.300 (b) | 7.957 (b) | 1.090 | − | 4.639 (b) | 5.523 (b) |
| 2 | (n,elastic) | 5.127 (b) | 5.784 (b) | 1.128 | − | 2.925 (b) | 4.199 (b) |
| 4 | (n,inelastic) | ( E-thr = 160.0 keV ) | 134.0 (mb) | 1.260 (b) | |||
| 16 | (n,2n) | ( E-thr = 7.009 MeV ) | 1.565 (b) | 7.324 (mb) | |||
| 17 | (n,3n) | ( E-thr = 16.66 MeV ) | − | 525.2 (nb) | |||
| 22 | (n,na) | ( E-thr = 3.803 MeV ) | 97.30 (μb) | 38.23 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.521 MeV ) | 102.6 (nb) | 37.26 (nb) | |||
| 32 | (n,nd) | ( E-thr = 14.04 MeV ) | − | 17.95e-12 (b) | |||
| 102 | (n,γ) | 2.174 (b) | 2.173 (b) | 1.000 | 18.15 (b) | 1.003 (mb) | 53.99 (mb) |
| 103 | (n,p) | ( E-thr = 678.2 keV ) | 11.80 (mb) | 9.011 (μb) | |||
| 104 | (n,d) | ( E-thr = 7.191 MeV ) | 553.2 (μb) | 163.3 (nb) | |||
| 105 | (n,t) | ( E-thr = 7.799 MeV ) | 76.12 (nb) | 4.433 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 42.43 (μb) | 2.289 (mb) | 3.635 (μb) |
|
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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