| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 6.307 (b) | 7.103 (b) | 1.126 | − | 3.842 (b) | 4.933 (b) |
| 2 | (n,elastic) | 6.197 (b) | 6.993 (b) | 1.128 | − | 2.541 (b) | 4.162 (b) |
| 4 | (n,inelastic) | ( E-thr = 892.6 keV ) | 334.7 (mb) | 758.8 (mb) | |||
| 16 | (n,2n) | ( E-thr = 10.65 MeV ) | 953.1 (mb) | 275.5 (μb) | |||
| 17 | (n,3n) | ( E-thr = 18.21 MeV ) | − | 25.41 (nb) | |||
| 22 | (n,na) | ( E-thr = 7.178 MeV ) | 38.03 (μb) | 70.65 (nb) | |||
| 28 | (n,np) | ( E-thr = 10.83 MeV ) | 592.4 (μb) | 548.0 (nb) | |||
| 102 | (n,γ) | 110.0 (mb) | 110.0 (mb) | 1.000 | 2.416 (b) | 1.019 (mb) | 10.01 (mb) |
| 103 | (n,p) | ( E-thr = 3.937 MeV ) | 8.014 (mb) | 7.975 (μb) | |||
| 104 | (n,d) | ( E-thr = 8.491 MeV ) | 55.21 (μb) | 46.43 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.95 MeV ) | 209.3e-12 (b) | 1.951 (nb) | |||
| 107 | (n,a) | ( E-thr = 391.3 keV ) | 2.611 (mb) | 1.461 (μb) | |||
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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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