| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 28.57 (b) | 29.02 (b) | 1.016 | − | 4.480 (b) | 5.761 (b) |
| 2 | (n,elastic) | 4.628 (b) | 5.219 (b) | 1.128 | − | 2.629 (b) | 4.268 (b) |
| 4 | (n,inelastic) | ( E-thr = 247.6 keV ) | 227.2 (mb) | 1.378 (b) | |||
| 16 | (n,2n) | ( E-thr = 7.045 MeV ) | 1.575 (b) | 6.184 (mb) | |||
| 17 | (n,3n) | ( E-thr = 17.02 MeV ) | − | 407.4 (nb) | |||
| 22 | (n,na) | ( E-thr = 3.335 MeV ) | 108.9 (μb) | 30.42 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.174 MeV ) | 311.3 (μb) | 106.5 (nb) | |||
| 32 | (n,nd) | ( E-thr = 13.72 MeV ) | 0.000 (b) | 132.0e-12 (b) | |||
| 102 | (n,γ) | 23.94 (b) | 23.80 (b) | 0.994 | 49.34 (b) | 1.006 (mb) | 108.9 (mb) |
| 103 | (n,p) | ( E-thr = 247.8 keV ) | 43.82 (mb) | 93.54 (μb) | |||
| 104 | (n,d) | ( E-thr = 6.843 MeV ) | 538.1 (μb) | 126.9 (nb) | |||
| 105 | (n,t) | ( E-thr = 7.474 MeV ) | 5.914 (μb) | 7.298 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 164.1 (μb) | 3.853 (mb) | 21.23 (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 :
|