| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 7.008 (b) | 7.627 (b) | 1.088 | − | 5.699 (b) | 6.984 (b) |
| 2 | (n,elastic) | 4.820 (b) | 5.438 (b) | 1.128 | − | 3.423 (b) | 5.068 (b) |
| 4 | (n,inelastic) | ( E-thr = 89.58 keV ) | 583.8 (mb) | 1.751 (b) | |||
| 16 | (n,2n) | ( E-thr = 8.596 MeV ) | 1.683 (b) | 2.134 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.08 MeV ) | − | 5.844 (μb) | |||
| 22 | (n,na) | ( E-thr = 198.2 keV ) | 66.50 (μb) | 22.19 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.056 MeV ) | 13.62 (μb) | 14.98 (nb) | |||
| 32 | (n,nd) | ( E-thr = 13.96 MeV ) | 0.000 (b) | 2.051e-12 (b) | |||
| 102 | (n,γ) | 2.188 (b) | 2.189 (b) | 1.000 | 120.5 (b) | 1.035 (mb) | 160.5 (mb) |
| 103 | (n,p) | ( E-thr = 1.681 MeV ) | 5.682 (mb) | 2.233 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.731 MeV ) | 128.8 (μb) | 51.42 (nb) | |||
| 105 | (n,t) | ( E-thr = 7.734 MeV ) | 3.150 (μb) | 6.547 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 16.03 (μb) | 2.358 (mb) | 1.423 (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 :
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