| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 19.10 (b) | 20.52 (b) | 1.074 | − | 4.976 (b) | 5.890 (b) |
| 2 | (n,elastic) | 11.10 (b) | 12.52 (b) | 1.128 | − | 3.292 (b) | 4.710 (b) |
| 4 | (n,inelastic) | ( E-thr = 446.4 keV ) | 278.4 (mb) | 1.081 (b) | |||
| 16 | (n,2n) | ( E-thr = 9.697 MeV ) | 1.376 (b) | 647.5 (μb) | |||
| 17 | (n,3n) | ( E-thr = 16.98 MeV ) | − | 472.4 (nb) | |||
| 22 | (n,na) | ( E-thr = 1.779 MeV ) | 568.9 (μb) | 149.4 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.239 MeV ) | 187.2 (μb) | 61.46 (nb) | |||
| 102 | (n,γ) | 8.002 (b) | 8.001 (b) | 1.000 | 12.46 (b) | 1.050 (mb) | 97.02 (mb) |
| 103 | (n,p) | ( E-thr = 1.355 MeV ) | 23.29 (mb) | 26.50 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.911 MeV ) | 177.6 (μb) | 58.88 (nb) | |||
| 105 | (n,t) | ( E-thr = 8.894 MeV ) | 202.6 (nb) | 3.387 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 149.5 (μb) | 4.000 (mb) | 9.928 (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 :
|