| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 6.218 (b) | 7.014 (b) | 1.128 | − | 3.842 (b) | 5.710 (b) |
| 2 | (n,elastic) | 6.167 (b) | 6.963 (b) | 1.129 | − | 2.140 (b) | 4.697 (b) |
| 4 | (n,inelastic) | ( E-thr = 928.6 keV ) | 297.0 (mb) | 1.004 (b) | |||
| 16 | (n,2n) | ( E-thr = 8.279 MeV ) | 1.396 (b) | 2.654 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.11 MeV ) | − | 1.143 (μb) | |||
| 22 | (n,na) | ( E-thr = 3.791 MeV ) | 245.8 (μb) | 58.27 (nb) | |||
| 28 | (n,np) | ( E-thr = 10.44 MeV ) | 6.552 (μb) | 9.436 (nb) | |||
| 32 | (n,nd) | ( E-thr = 15.67 MeV ) | − | 7.433e-12 (b) | |||
| 102 | (n,γ) | 50.69 (mb) | 50.72 (mb) | 1.001 | 287.1 (mb) | 550.1 (μb) | 4.998 (mb) |
| 103 | (n,p) | ( E-thr = 4.143 MeV ) | 8.114 (mb) | 3.021 (μb) | |||
| 104 | (n,d) | ( E-thr = 8.107 MeV ) | 29.82 (μb) | 23.85 (nb) | |||
| 105 | (n,t) | ( E-thr = 9.416 MeV ) | 8.044 (μb) | 9.113 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 115.2 (μb) | 4.171 (mb) | 5.698 (μb) |
|
These cross sections are calculated from JENDL-4.0 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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