| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 3.464 (b) | 3.836 (b) | 1.107 | − | 4.896 (b) | 6.266 (b) |
| 2 | (n,elastic) | 2.894 (b) | 3.266 (b) | 1.128 | − | 2.809 (b) | 5.447 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.608 MeV ) | 332.9 (mb) | 810.8 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.257 MeV ) | 1.742 (b) | 1.049 (mb) | |||
| 17 | (n,3n) | ( E-thr = 16.79 MeV ) | − | 485.3 (nb) | |||
| 22 | (n,na) | ( E-thr = 1.608 MeV ) | 476.1 (μb) | 128.7 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.202 MeV ) | 139.7 (μb) | 62.59 (nb) | |||
| 32 | (n,nd) | ( E-thr = 14.72 MeV ) | − | 651.9e-15 (b) | |||
| 102 | (n,γ) | 570.4 (mb) | 570.4 (mb) | 1.000 | 340.7 (mb) | 2.001 (mb) | 6.126 (mb) |
| 103 | (n,p) | ( E-thr = 3.000 MeV ) | 5.999 (mb) | 1.880 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.876 MeV ) | 292.3 (μb) | 91.98 (nb) | |||
| 105 | (n,t) | ( E-thr = 8.492 MeV ) | 1.383 (μb) | 6.217 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 56.51 (μb) | 3.815 (mb) | 3.681 (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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