| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 30.99 (b) | 34.39 (b) | 1.110 | − | 2.662 (b) | 3.836 (b) |
| 2 | (n,elastic) | 26.48 (b) | 29.88 (b) | 1.128 | − | 1.296 (b) | 3.389 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.480 MeV ) | 296.6 (mb) | 324.9 (mb) | |||
| 16 | (n,2n) | ( E-thr = 12.42 MeV ) | 21.50 (mb) | 2.984 (μb) | |||
| 22 | (n,na) | ( E-thr = 6.520 MeV ) | 9.800 (mb) | 1.940 (μb) | |||
| 28 | (n,np) | ( E-thr = 8.320 MeV ) | 560.0 (mb) | 218.9 (μb) | |||
| 102 | (n,γ) | 4.505 (b) | 4.504 (b) | 1.000 | 2.155 (b) | 53.98 (μb) | 8.475 (mb) |
| 103 | (n,p) | 189.7e-15 (b) | 428.1e-15 (b) | 2.257 | 622.5 (mb) | 364.0 (mb) | 107.0 (mb) |
| 104 | (n,d) | ( E-thr = 5.968 MeV ) | 10.20 (mb) | 3.185 (μb) | |||
| 105 | (n,t) | ( E-thr = 11.25 MeV ) | 11.00 (μb) | 66.81 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 6.589 MeV ) | 9.990 (μb) | 2.908 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 65.82 (mb) | 91.90 (mb) | 6.178 (mb) |
| 111 | (n,2p) | ( E-thr = 6.671 MeV ) | 11.80 (mb) | 2.174 (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 :
|