| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 26.95 (b) | 27.99 (b) | 1.039 | − | 5.435 (b) | 6.731 (b) |
| 2 | (n,elastic) | 8.028 (b) | 9.053 (b) | 1.128 | − | 2.689 (b) | 4.771 (b) |
| 4 | (n,inelastic) | ( E-thr = 102.6 keV ) | 1.047 (b) | 1.780 (b) | |||
| 16 | (n,2n) | ( E-thr = 9.267 MeV ) | 1.683 (b) | 832.2 (μb) | |||
| 17 | (n,3n) | ( E-thr = 16.53 MeV ) | − | 165.4 (nb) | |||
| 22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 5.786 (μb) | 459.6 (μb) | 317.3 (nb) |
| 28 | (n,np) | ( E-thr = 6.468 MeV ) | 436.1 (μb) | 119.9 (nb) | |||
| 102 | (n,γ) | 18.92 (b) | 18.93 (b) | 1.001 | 451.9 (b) | 1.630 (mb) | 179.3 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 218.3 (μb) | 9.077 (mb) | 10.42 (μb) |
| 104 | (n,d) | ( E-thr = 4.230 MeV ) | 1.026 (mb) | 238.1 (nb) | |||
| 105 | (n,t) | ( E-thr = 6.870 MeV ) | 2.374 (μb) | 1.735 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 169.0 (μb) | 2.876 (mb) | 16.59 (μb) |
|
These cross sections are calculated from JENDL-3.3 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 :
|