| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 20.78 (kb) | 27.76 (kb) | 1.336 | − | 4.480 (b) | 5.575 (b) |
| 2 | (n,elastic) | 25.86 (b) | 58.19 (b) | 2.250 | − | 2.658 (b) | 4.072 (b) |
| 4 | (n,inelastic) | ( E-thr = 266.0 keV ) | 182.7 (mb) | 1.414 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.607 MeV ) | 1.628 (b) | 9.860 (mb) | |||
| 17 | (n,3n) | ( E-thr = 16.09 MeV ) | − | 1.261 (μb) | |||
| 22 | (n,na) | ( E-thr = 3.901 MeV ) | 19.46 (μb) | 8.960 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.811 MeV ) | 17.94 (μb) | 19.32 (nb) | |||
| 32 | (n,nd) | ( E-thr = 14.01 MeV ) | − | 79.17e-12 (b) | |||
| 102 | (n,γ) | 20.76 (kb) | 27.70 (kb) | 1.334 | 394.5 (b) | 1.001 (mb) | 75.56 (mb) |
| 103 | (n,p) | ( E-thr = 1.239 MeV ) | 9.096 (mb) | 5.921 (μb) | |||
| 104 | (n,d) | ( E-thr = 7.480 MeV ) | 208.2 (μb) | 63.13 (nb) | |||
| 105 | (n,t) | ( E-thr = 7.768 MeV ) | 4.299 (μb) | 7.304 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 22.37 (μb) | 1.809 (mb) | 2.269 (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 :
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