MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 2.693 (kb) | 2.704 (kb) | 1.004 | − | 5.903 (b) | 7.950 (b) |
2 | (n,elastic) | 12.26 (b) | 13.66 (b) | 1.115 | − | 2.806 (b) | 4.418 (b) |
4 | (n,inelastic) | ( E-thr = 26.54 keV ) | 380.6 (mb) | 2.015 (b) | |||
16 | (n,2n) | ( E-thr = 5.512 MeV ) | 488.3 (mb) | 13.27 (mb) | |||
17 | (n,3n) | ( E-thr = 12.12 MeV ) | 22.49 (mb) | 4.759 (μb) | |||
18 | (n,fission) | 2.202 (kb) | 2.226 (kb) | 1.011 | 1.098 (kb) | 2.200 (b) | 1.451 (b) |
19 | (n,f) | 2.202 (kb) | 2.226 (kb) | 1.011 | 1.098 (kb) | 1.188 (b) | 1.441 (b) |
20 | (n,nf) | ( E-thr = 3.000 MeV ) | 716.0 (mb) | 9.416 (mb) | |||
21 | (n,2nf) | ( E-thr = 7.500 MeV ) | 296.5 (mb) | 47.86 (μb) | |||
37 | (n,4n) | ( E-thr = 17.88 MeV ) | − | 202.3e-12 (b) | |||
38 | (n,3nf) | ( E-thr = 14.50 MeV ) | − | 983.8e-12 (b) | |||
102 | (n,γ) | 479.5 (b) | 464.0 (b) | 0.968 | 201.4 (b) | 1.131 (mb) | 51.40 (mb) |
456 | νp | 2.470 | − | − | − | 4.510 | − |
455 | νd | 1.494e-2 | − | − | − | 1.235e-2 | − |
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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