| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 3.086 (b) | 3.438 (b) | 1.114 | − | 2.500 (b) | 3.569 (b) |
| 2 | (n,elastic) | 2.743 (b) | 3.096 (b) | 1.128 | − | 1.249 (b) | 2.879 (b) |
| 4 | (n,inelastic) | ( E-thr = 850.5 keV ) | 548.6 (mb) | 687.4 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.902 MeV ) | 676.1 (mb) | 259.7 (μb) | |||
| 22 | (n,na) | ( E-thr = 8.072 MeV ) | 833.5 (μb) | 270.6 (nb) | |||
| 28 | (n,np) | ( E-thr = 12.59 MeV ) | 1.131 (μb) | 108.5 (nb) | |||
| 102 | (n,γ) | 342.7 (mb) | 342.7 (mb) | 1.000 | 178.0 (mb) | 445.3 (μb) | 1.294 (mb) |
| 103 | (n,p) | ( E-thr = 6.336 MeV ) | 12.47 (mb) | 6.136 (μb) | |||
| 104 | (n,d) | ( E-thr = 10.34 MeV ) | 231.4 (μb) | 75.87 (nb) | |||
| 105 | (n,t) | ( E-thr = 12.60 MeV ) | 6.223 (nb) | 896.4e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 14.59 MeV ) | − | 83.71e-15 (b) | |||
| 107 | (n,a) | ( E-thr = 1.575 MeV ) | 12.36 (mb) | 38.51 (μb) | |||
| 111 | (n,2p) | ( E-thr = 16.92 MeV ) | − | 8.959e-18 (b) | |||
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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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