MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 85.83 (b) | 88.20 (b) | 1.028 | − | 5.599 (b) | 7.701 (b) |
2 | (n,elastic) | 6.490 (b) | 7.276 (b) | 1.121 | − | 2.377 (b) | 4.581 (b) |
4 | (n,inelastic) | ( E-thr = 42.38 keV ) | 357.2 (mb) | 1.847 (b) | |||
16 | (n,2n) | ( E-thr = 6.391 MeV ) | 595.3 (mb) | 3.530 (mb) | |||
17 | (n,3n) | ( E-thr = 11.95 MeV ) | 61.21 (mb) | 7.460 (μb) | |||
18 | (n,fission) | 81.58 (mb) | 82.97 (mb) | 1.017 | 6.308 (b) | 2.205 (b) | 1.081 (b) |
19 | (n,f) | 81.58 (mb) | 82.97 (mb) | 1.017 | 5.919 (b) | 1.255 (b) | 1.062 (b) |
20 | (n,nf) | ( E-thr = 2.300 MeV ) | 917.8 (mb) | 18.43 (mb) | |||
21 | (n,2nf) | ( E-thr = 9.000 MeV ) | 34.25 (mb) | 7.259 (μb) | |||
37 | (n,4n) | ( E-thr = 18.63 MeV ) | − | 525.0e-15 (b) | |||
38 | (n,3nf) | ( E-thr = 14.50 MeV ) | − | 2.137 (nb) | |||
102 | (n,γ) | 79.26 (b) | 80.83 (b) | 1.020 | 2.040 (kb) | 1.196 (mb) | 185.9 (mb) |
456 | νp | 3.187 | − | − | − | 5.374 | − |
455 | νd | 8.500e-3 | − | − | − | 7.679e-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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