MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 5.998 (b) | 6.612 (b) | 1.102 | − | 4.927 (b) | 6.744 (b) |
2 | (n,elastic) | 4.796 (b) | 5.412 (b) | 1.128 | − | 2.274 (b) | 4.736 (b) |
4 | (n,inelastic) | ( E-thr = 131.0 keV ) | 644.1 (mb) | 1.974 (b) | |||
16 | (n,2n) | ( E-thr = 7.434 MeV ) | 1.800 (b) | 5.533 (mb) | |||
17 | (n,3n) | ( E-thr = 12.51 MeV ) | 204.3 (mb) | 29.83 (μb) | |||
22 | (n,na) | ( E-thr = 346.2 keV ) | 129.9 (μb) | 49.70 (nb) | |||
28 | (n,np) | ( E-thr = 9.670 MeV ) | 2.939 (nb) | 11.35 (nb) | |||
32 | (n,nd) | ( E-thr = 14.33 MeV ) | − | 2.569e-12 (b) | |||
33 | (n,nt) | ( E-thr = 13.28 MeV ) | 0.000 (b) | 31.70e-12 (b) | |||
102 | (n,γ) | 1.202 (b) | 1.200 (b) | 0.998 | 15.90 (b) | 1.010 (mb) | 27.85 (mb) |
103 | (n,p) | ( E-thr = 4.248 MeV ) | 1.145 (mb) | 262.7 (nb) | |||
104 | (n,d) | ( E-thr = 7.345 MeV ) | 13.01 (μb) | 43.37 (nb) | |||
105 | (n,t) | ( E-thr = 8.101 MeV ) | 8.147 (μb) | 17.64 (nb) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 2.259 (μb) | 1.638 (mb) | 447.1 (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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