MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 813.1 (b) | 816.3 (b) | 1.004 | − | 5.822 (b) | 7.617 (b) |
2 | (n,elastic) | 12.53 (b) | 14.15 (b) | 1.129 | − | 2.791 (b) | 4.510 (b) |
4 | (n,inelastic) | ( E-thr = 27.49 keV ) | 445.1 (mb) | 2.972 (b) | |||
16 | (n,2n) | ( E-thr = 6.560 MeV ) | 2.170 (b) | 15.87 (mb) | |||
17 | (n,3n) | ( E-thr = 11.98 MeV ) | 352.7 (mb) | 55.64 (μb) | |||
18 | (n,fission) | 100.0 (μb) | 99.88 (μb) | 0.999 | 57.43 (mb) | 62.79 (mb) | 12.16 (mb) |
19 | (n,f) | 100.0 (μb) | 99.88 (μb) | 0.999 | 49.20 (mb) | 25.72 (mb) | 11.88 (mb) |
20 | (n,nf) | ( E-thr = 3.000 MeV ) | 35.97 (mb) | 276.5 (μb) | |||
21 | (n,2nf) | ( E-thr = 9.500 MeV ) | 1.117 (mb) | 831.5 (nb) | |||
37 | (n,4n) | ( E-thr = 18.68 MeV ) | − | 234.1e-12 (b) | |||
38 | (n,3nf) | ( E-thr = 15.50 MeV ) | − | 32.29e-12 (b) | |||
102 | (n,γ) | 800.3 (b) | 800.6 (b) | 1.000 | 1.018 (kb) | 1.119 (mb) | 105.7 (mb) |
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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