MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 106.8 (b) | 108.0 (b) | 1.012 | − | 5.008 (b) | 6.622 (b) |
2 | (n,elastic) | 6.622 (b) | 7.472 (b) | 1.128 | − | 3.240 (b) | 4.481 (b) |
4 | (n,inelastic) | ( E-thr = 22.75 keV ) | 197.4 (mb) | 2.065 (b) | |||
16 | (n,2n) | ( E-thr = 6.375 MeV ) | 1.566 (b) | 11.92 (mb) | |||
17 | (n,3n) | ( E-thr = 14.60 MeV ) | − | 5.089 (μb) | |||
22 | (n,na) | ( E-thr = 1.223 MeV ) | 20.69 (μb) | 9.315 (nb) | |||
28 | (n,np) | ( E-thr = 7.227 MeV ) | 97.90 (μb) | 42.37 (nb) | |||
32 | (n,nd) | ( E-thr = 10.76 MeV ) | 24.69e-15 (b) | 2.829 (nb) | |||
33 | (n,nt) | ( E-thr = 12.56 MeV ) | 0.000 (b) | 45.77e-12 (b) | |||
102 | (n,γ) | 100.0 (b) | 100.0 (b) | 1.000 | 1.449 (kb) | 1.000 (mb) | 63.57 (mb) |
103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 7.730 (μb) | 2.139 (mb) | 821.5 (nb) |
104 | (n,d) | ( E-thr = 4.902 MeV ) | 391.6 (μb) | 110.5 (nb) | |||
105 | (n,t) | ( E-thr = 4.533 MeV ) | 42.22 (μb) | 20.92 (nb) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 4.723 (μb) | 876.3 (μb) | 404.8 (nb) |
These cross sections are calculated from JENDL-3.3 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 :
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