MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 2.758 (kb) | 2.930 (kb) | 1.062 | − | 5.645 (b) | 7.793 (b) |
2 | (n,elastic) | 7.386 (b) | 8.284 (b) | 1.122 | − | 2.497 (b) | 4.422 (b) |
4 | (n,inelastic) | ( E-thr = 44.28 keV ) | 405.5 (mb) | 1.493 (b) | |||
16 | (n,2n) | ( E-thr = 5.561 MeV ) | 220.2 (mb) | 7.430 (mb) | |||
17 | (n,3n) | ( E-thr = 12.24 MeV ) | 3.114 (mb) | 1.068 (μb) | |||
18 | (n,fission) | 2.421 (kb) | 2.569 (kb) | 1.061 | 1.055 (kb) | 2.518 (b) | 1.833 (b) |
19 | (n,f) | 2.421 (kb) | 2.569 (kb) | 1.061 | 1.055 (kb) | 1.387 (b) | 1.823 (b) |
20 | (n,nf) | ( E-thr = 2.500 MeV ) | 994.8 (mb) | 9.657 (mb) | |||
21 | (n,2nf) | ( E-thr = 7.500 MeV ) | 135.8 (mb) | 21.14 (μb) | |||
37 | (n,4n) | ( E-thr = 18.21 MeV ) | − | 6.943e-12 (b) | |||
38 | (n,3nf) | ( E-thr = 15.50 MeV ) | − | 140.0e-12 (b) | |||
102 | (n,γ) | 330.3 (b) | 353.5 (b) | 1.070 | 204.8 (b) | 1.026 (mb) | 36.07 (mb) |
456 | νp | 3.264 | − | − | − | 5.155 | − |
455 | νd | 6.659e-3 | − | − | − | 5.775e-3 | − |
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 :
νp,
νd
: numbers of prompt and delayed neutrons per fission.
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