| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 19.59 (b) | 20.30 (b) | 1.036 | − | 4.338 (b) | 5.666 (b) |
| 2 | (n,elastic) | 5.596 (b) | 6.312 (b) | 1.128 | − | 2.559 (b) | 4.193 (b) |
| 4 | (n,inelastic) | ( E-thr = 206.3 keV ) | 371.5 (mb) | 1.421 (b) | |||
| 16 | (n,2n) | ( E-thr = 7.453 MeV ) | 1.346 (b) | 2.517 (mb) | |||
| 17 | (n,3n) | ( E-thr = 17.23 MeV ) | − | 98.24 (nb) | |||
| 22 | (n,na) | ( E-thr = 2.269 MeV ) | 3.044 (mb) | 1.248 (μb) | |||
| 28 | (n,np) | ( E-thr = 8.730 MeV ) | 8.369 (mb) | 1.806 (μb) | |||
| 102 | (n,γ) | 14.00 (b) | 13.99 (b) | 0.999 | 118.5 (b) | 1.002 (mb) | 45.45 (mb) |
| 103 | (n,p) | ( E-thr = 144.7 keV ) | 35.23 (mb) | 241.1 (μb) | |||
| 104 | (n,d) | ( E-thr = 6.396 MeV ) | 1.538 (mb) | 313.9 (nb) | |||
| 105 | (n,t) | ( E-thr = 7.456 MeV ) | 80.32 (μb) | 26.90 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 7.530 MeV ) | 433.9e-12 (b) | 72.91e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 7.935 (mb) | 13.33 (mb) | 1.504 (mb) |
|
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 :
|