| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 4.554 (b) | 5.121 (b) | 1.125 | − | 4.638 (b) | 5.519 (b) |
| 2 | (n,elastic) | 4.418 (b) | 4.986 (b) | 1.128 | − | 2.929 (b) | 4.758 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.141 MeV ) | 192.0 (mb) | 751.0 (mb) | |||
| 16 | (n,2n) | ( E-thr = 8.564 MeV ) | 1.515 (b) | 2.352 (mb) | |||
| 17 | (n,3n) | ( E-thr = 14.56 MeV ) | − | 4.699 (μb) | |||
| 22 | (n,na) | ( E-thr = 6.735 MeV ) | 101.6e-12 (b) | 72.76e-12 (b) | |||
| 28 | (n,np) | ( E-thr = 12.19 MeV ) | 68.32e-21 (b) | 524.0e-12 (b) | |||
| 102 | (n,γ) | 135.5 (mb) | 135.4 (mb) | 0.999 | 7.848 (b) | 1.000 (mb) | 6.319 (mb) |
| 103 | (n,p) | ( E-thr = 6.409 MeV ) | 951.7 (μb) | 218.9 (nb) | |||
| 104 | (n,d) | ( E-thr = 9.863 MeV ) | 55.41e-15 (b) | 1.220 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.61 MeV ) | 1.093e-18 (b) | 292.0e-12 (b) | |||
| 107 | (n,a) | ( E-thr = 1.268 MeV ) | 4.269 (μb) | 2.819 (nb) | |||
|
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 :
|