MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 56.13 (b) | 57.63 (b) | 1.027 | − | 5.906 (b) | 7.944 (b) |
2 | (n,elastic) | 11.02 (b) | 12.45 (b) | 1.129 | − | 2.823 (b) | 4.646 (b) |
4 | (n,inelastic) | ( E-thr = 31.26 keV ) | 351.9 (mb) | 2.580 (b) | |||
16 | (n,2n) | ( E-thr = 6.241 MeV ) | 1.102 (b) | 9.275 (mb) | |||
17 | (n,3n) | ( E-thr = 11.75 MeV ) | 188.8 (mb) | 24.64 (μb) | |||
18 | (n,fission) | 28.01 (mb) | 28.06 (mb) | 1.002 | 2.247 (b) | 1.435 (b) | 590.4 (mb) |
19 | (n,f) | 28.01 (mb) | 28.06 (mb) | 1.002 | 1.800 (b) | 519.5 (mb) | 568.8 (mb) |
20 | (n,nf) | ( E-thr = 2.300 MeV ) | 786.9 (mb) | 21.77 (mb) | |||
21 | (n,2nf) | ( E-thr = 9.500 MeV ) | 129.2 (mb) | 20.41 (μb) | |||
37 | (n,4n) | ( E-thr = 18.36 MeV ) | − | 40.90e-12 (b) | |||
38 | (n,3nf) | ( E-thr = 14.00 MeV ) | 0.000 (b) | 17.93 (nb) | |||
102 | (n,γ) | 45.02 (b) | 45.03 (b) | 1.000 | 931.8 (b) | 1.257 (mb) | 116.7 (mb) |
456 | νp | 2.699 | − | − | − | 4.471 | − |
455 | νd | 2.186e-2 | − | − | − | 1.494e-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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