MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 4.232 (b) | 4.734 (b) | 1.119 | − | 4.482 (b) | 5.869 (b) |
2 | (n,elastic) | 3.891 (b) | 4.393 (b) | 1.129 | − | 2.400 (b) | 4.343 (b) |
4 | (n,inelastic) | ( E-thr = 563.4 keV ) | 452.6 (mb) | 1.497 (b) | |||
16 | (n,2n) | ( E-thr = 9.123 MeV ) | 1.624 (b) | 1.402 (mb) | |||
17 | (n,3n) | ( E-thr = 15.72 MeV ) | − | 642.3 (nb) | |||
22 | (n,na) | ( E-thr = 4.133 MeV ) | 12.64 (μb) | 8.749 (nb) | |||
28 | (n,np) | ( E-thr = 10.37 MeV ) | 8.994 (μb) | 44.68 (nb) | |||
32 | (n,nd) | ( E-thr = 16.68 MeV ) | − | 21.47e-15 (b) | |||
102 | (n,γ) | 340.5 (mb) | 340.7 (mb) | 1.001 | 16.86 (b) | 763.9 (μb) | 27.47 (mb) |
103 | (n,p) | ( E-thr = 4.328 MeV ) | 6.616 (mb) | 1.993 (μb) | |||
104 | (n,d) | ( E-thr = 8.124 MeV ) | 50.81 (μb) | 70.83 (nb) | |||
105 | (n,t) | ( E-thr = 10.37 MeV ) | 42.12 (nb) | 2.907 (nb) | |||
106 | (n,He-3) | ( E-thr = 10.64 MeV ) | 146.3e-21 (b) | 307.8e-18 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 1.679 (μb) | 545.3 (μb) | 194.0 (nb) |
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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