MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 478.5 (b) | 470.4 (b) | 0.983 | − | 5.899 (b) | 7.958 (b) |
2 | (n,elastic) | 24.44 (b) | 26.88 (b) | 1.100 | − | 2.812 (b) | 4.433 (b) |
4 | (n,inelastic) | ( E-thr = 11.44 keV ) | 498.4 (mb) | 2.822 (b) | |||
16 | (n,2n) | ( E-thr = 5.148 MeV ) | 933.8 (mb) | 33.74 (mb) | |||
17 | (n,3n) | ( E-thr = 11.72 MeV ) | 247.2 (mb) | 34.99 (μb) | |||
18 | (n,fission) | 1.702 (b) | 1.674 (b) | 0.983 | 45.87 (b) | 1.399 (b) | 594.5 (mb) |
19 | (n,f) | 1.702 (b) | 1.674 (b) | 0.983 | 45.67 (b) | 431.1 (mb) | 586.7 (mb) |
20 | (n,nf) | ( E-thr = 4.000 MeV ) | 480.6 (mb) | 7.715 (mb) | |||
21 | (n,2nf) | ( E-thr = 9.500 MeV ) | 487.3 (mb) | 90.82 (μb) | |||
37 | (n,4n) | ( E-thr = 17.04 MeV ) | − | 12.77 (nb) | |||
38 | (n,3nf) | ( E-thr = 16.00 MeV ) | − | 14.41 (nb) | |||
102 | (n,γ) | 452.3 (b) | 441.8 (b) | 0.977 | 1.077 (kb) | 823.1 (μb) | 73.36 (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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