| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 6.189 (b) | 6.984 (b) | 1.128 | − | 3.842 (b) | 5.070 (b) |
| 2 | (n,elastic) | 6.186 (b) | 6.981 (b) | 1.128 | − | 2.516 (b) | 4.562 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.583 MeV ) | 334.0 (mb) | 506.0 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.983 MeV ) | 984.1 (mb) | 468.3 (μb) | |||
| 17 | (n,3n) | ( E-thr = 17.18 MeV ) | − | 105.8 (nb) | |||
| 22 | (n,na) | ( E-thr = 8.194 MeV ) | 440.4 (nb) | 9.529 (nb) | |||
| 28 | (n,np) | ( E-thr = 12.03 MeV ) | 84.57 (nb) | 9.324 (nb) | |||
| 102 | (n,γ) | 3.001 (mb) | 3.000 (mb) | 1.000 | 22.72 (mb) | 1.002 (mb) | 1.615 (mb) |
| 103 | (n,p) | ( E-thr = 6.597 MeV ) | 5.603 (mb) | 1.243 (μb) | |||
| 104 | (n,d) | ( E-thr = 9.689 MeV ) | 3.697 (μb) | 21.11 (nb) | |||
| 105 | (n,t) | ( E-thr = 12.52 MeV ) | 91.73e-15 (b) | 1.508 (nb) | |||
| 107 | (n,a) | ( E-thr = 2.225 MeV ) | 830.6 (μb) | 236.8 (nb) | |||
|
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 :
|