MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 13.75 (b) | 15.35 (b) | 1.116 | − | 5.872 (b) | 7.741 (b) |
2 | (n,elastic) | 11.93 (b) | 13.47 (b) | 1.129 | − | 2.772 (b) | 4.918 (b) |
4 | (n,inelastic) | ( E-thr = 49.76 keV ) | 454.6 (mb) | 2.726 (b) | |||
16 | (n,2n) | ( E-thr = 6.217 MeV ) | 1.506 (b) | 23.91 (mb) | |||
17 | (n,3n) | ( E-thr = 11.02 MeV ) | 936.6 (mb) | 142.6 (μb) | |||
18 | (n,fission) | 5.002 (mb) | 5.007 (mb) | 1.001 | 195.7 (mb) | 202.2 (mb) | 33.95 (mb) |
19 | (n,f) | 5.002 (mb) | 5.007 (mb) | 1.001 | 121.6 (mb) | 85.61 (mb) | 30.01 (mb) |
20 | (n,nf) | ( E-thr = 2.700 MeV ) | 95.01 (mb) | 3.946 (mb) | |||
21 | (n,2nf) | ( E-thr = 8.500 MeV ) | 21.60 (mb) | 3.421 (μb) | |||
37 | (n,4n) | ( E-thr = 17.49 MeV ) | − | 12.42 (nb) | |||
38 | (n,3nf) | ( E-thr = 14.00 MeV ) | 0.000 (b) | 20.11 (nb) | |||
102 | (n,γ) | 1.801 (b) | 1.802 (b) | 1.001 | 31.40 (b) | 1.007 (mb) | 37.17 (mb) |
456 | νp | 1.862 | − | − | − | 3.598 | − |
455 | νd | 1.096e-1 | − | − | − | 7.440e-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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