| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 12.24 (b) | 13.58 (b) | 1.109 | − | 1.578 (b) | 1.964 (b) |
| 2 | (n,elastic) | 10.37 (b) | 11.70 (b) | 1.128 | − | 984.1 (mb) | 1.832 (b) |
| 4 | (n,inelastic) | ( E-thr = 2.480 MeV ) | 399.3 (mb) | 11.36 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.31 MeV ) | 5.670 (mb) | 1.006 (μb) | |||
| 22 | (n,na) | ( E-thr = 12.45 MeV ) | 29.95 (μb) | 113.6 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.095 MeV ) | 44.52 (mb) | 22.89 (μb) | |||
| 32 | (n,nd) | ( E-thr = 11.01 MeV ) | 3.826 (mb) | 654.7 (nb) | |||
| 102 | (n,γ) | 75.00 (mb) | 75.03 (mb) | 1.000 | 33.85 (mb) | 1.036 (μb) | 34.69 (μb) |
| 103 | (n,p) | 1.769 (b) | 1.769 (b) | 1.000 | 908.6 (mb) | 4.200 (mb) | 34.76 (mb) |
| 104 | (n,d) | ( E-thr = 5.710 MeV ) | 32.66 (mb) | 319.6 (μb) | |||
| 105 | (n,t) | ( E-thr = 4.304 MeV ) | 10.00 (mb) | 773.8 (μb) | |||
| 107 | (n,a) | ( E-thr = 169.4 keV ) | 60.10 (mb) | 84.07 (mb) | |||
| 108 | (n,2a) | ( E-thr = 9.458 MeV ) | 34.48 (mb) | 5.639 (μb) | |||
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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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