| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 9.814 (b) | 10.97 (b) | 1.117 | − | 3.303 (b) | 4.071 (b) |
| 2 | (n,elastic) | 8.928 (b) | 10.08 (b) | 1.129 | − | 1.757 (b) | 3.049 (b) |
| 4 | (n,inelastic) | 0.000 (b) | 0.000 (b) | − | 3.511 (b) | 643.5 (mb) | 1.008 (b) |
| 16 | (n,2n) | ( E-thr = 10.90 MeV ) | 848.2 (mb) | 191.6 (μb) | |||
| 17 | (n,3n) | ( E-thr = 18.42 MeV ) | − | 2.237 (nb) | |||
| 22 | (n,na) | ( E-thr = 5.077 MeV ) | 5.924 (mb) | 4.566 (μb) | |||
| 24 | (n,2na) | ( E-thr = 15.42 MeV ) | − | 107.6e-15 (b) | |||
| 28 | (n,np) | ( E-thr = 9.874 MeV ) | 6.065 (mb) | 1.317 (μb) | |||
| 102 | (n,γ) | 885.9 (mb) | 886.4 (mb) | 1.001 | 903.7 (mb) | 531.4 (μb) | 12.85 (mb) |
| 103 | (n,p) | ( E-thr = 3.262 MeV ) | 34.16 (mb) | 162.1 (μb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 1.937 (mb) | 9.440 (mb) | 93.74 (μb) |
| 112 | (n,pa) | ( E-thr = 8.808 MeV ) | 11.66e-12 (b) | 7.846e-12 (b) | |||
|
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 :
|