MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 620.1 (b) | 623.4 (b) | 1.005 | − | 5.849 (b) | 7.400 (b) |
2 | (n,elastic) | 12.53 (b) | 14.15 (b) | 1.129 | − | 2.750 (b) | 4.544 (b) |
4 | (n,inelastic) | ( E-thr = 9.331 keV ) | 444.8 (mb) | 2.368 (b) | |||
16 | (n,2n) | ( E-thr = 5.486 MeV ) | 1.898 (b) | 27.03 (mb) | |||
17 | (n,3n) | ( E-thr = 12.70 MeV ) | 33.25 (mb) | 15.18 (μb) | |||
18 | (n,fission) | 202.1 (b) | 202.2 (b) | 1.001 | 330.5 (b) | 722.1 (mb) | 297.0 (mb) |
19 | (n,f) | 202.1 (b) | 202.2 (b) | 1.001 | 330.4 (b) | 277.0 (mb) | 294.1 (mb) |
20 | (n,nf) | ( E-thr = 2.700 MeV ) | 444.9 (mb) | 2.845 (mb) | |||
21 | (n,2nf) | ( E-thr = 9.500 MeV ) | 2.955 (μb) | 23.20 (nb) | |||
37 | (n,4n) | ( E-thr = 18.49 MeV ) | − | 95.59e-12 (b) | |||
38 | (n,3nf) | ( E-thr = 17.00 MeV ) | − | 98.46e-21 (b) | |||
102 | (n,γ) | 405.2 (b) | 405.4 (b) | 1.001 | 661.4 (b) | 1.348 (mb) | 163.4 (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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