MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 194.3 (b) | 194.8 (b) | 1.003 | − | 4.871 (b) | 5.891 (b) |
2 | (n,elastic) | 3.615 (b) | 4.080 (b) | 1.129 | − | 2.810 (b) | 4.343 (b) |
4 | (n,inelastic) | ( E-thr = 235.0 keV ) | 169.6 (mb) | 1.528 (b) | |||
16 | (n,2n) | ( E-thr = 6.483 MeV ) | 1.878 (b) | 8.196 (mb) | |||
17 | (n,3n) | ( E-thr = 15.49 MeV ) | − | 1.460 (μb) | |||
22 | (n,na) | ( E-thr = 3.089 MeV ) | 13.67 (μb) | 5.656 (nb) | |||
28 | (n,np) | ( E-thr = 9.303 MeV ) | 76.47 (μb) | 86.25 (nb) | |||
32 | (n,nd) | ( E-thr = 13.44 MeV ) | 13.15e-27 (b) | 34.81e-12 (b) | |||
102 | (n,γ) | 190.1 (b) | 190.2 (b) | 1.001 | 89.06 (b) | 928.5 (μb) | 11.30 (mb) |
103 | (n,p) | ( E-thr = 982.0 keV ) | 15.71 (mb) | 12.82 (μb) | |||
104 | (n,d) | ( E-thr = 7.061 MeV ) | 481.0 (μb) | 114.7 (nb) | |||
105 | (n,t) | ( E-thr = 7.131 MeV ) | 8.766 (μb) | 4.102 (nb) | |||
106 | (n,He-3) | ( E-thr = 9.365 MeV ) | 169.7e-18 (b) | 14.86e-15 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 18.08 (μb) | 834.9 (μb) | 1.382 (μb) |
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 :
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