| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 4.505 (b) | 5.068 (b) | 1.125 | − | 3.842 (b) | 4.952 (b) |
| 2 | (n,elastic) | 4.385 (b) | 4.948 (b) | 1.128 | − | 2.243 (b) | 4.058 (b) |
| 4 | (n,inelastic) | ( E-thr = 407.7 keV ) | 347.5 (mb) | 889.1 (mb) | |||
| 16 | (n,2n) | ( E-thr = 10.05 MeV ) | 1.237 (b) | 535.6 (μb) | |||
| 17 | (n,3n) | ( E-thr = 18.80 MeV ) | − | 4.564 (nb) | |||
| 22 | (n,na) | ( E-thr = 8.085 MeV ) | 1.804 (μb) | 35.51 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.726 MeV ) | 881.5 (μb) | 198.4 (nb) | |||
| 32 | (n,nd) | ( E-thr = 16.37 MeV ) | − | 3.066e-12 (b) | |||
| 102 | (n,γ) | 120.0 (mb) | 120.0 (mb) | 1.000 | 2.713 (b) | 1.012 (mb) | 3.046 (mb) |
| 103 | (n,p) | ( E-thr = 3.142 MeV ) | 10.36 (mb) | 8.029 (μb) | |||
| 104 | (n,d) | ( E-thr = 6.390 MeV ) | 307.9 (μb) | 101.7 (nb) | |||
| 105 | (n,t) | ( E-thr = 10.11 MeV ) | 172.4 (nb) | 3.380 (nb) | |||
| 107 | (n,a) | ( E-thr = 1.196 MeV ) | 2.867 (mb) | 924.7 (nb) | |||
|
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 :
|