MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 26.44 (b) | 27.43 (b) | 1.037 | − | 4.781 (b) | 6.379 (b) |
2 | (n,elastic) | 7.728 (b) | 8.720 (b) | 1.128 | − | 2.842 (b) | 5.568 (b) |
4 | (n,inelastic) | ( E-thr = 1.587 MeV ) | 356.9 (mb) | 753.7 (mb) | |||
16 | (n,2n) | ( E-thr = 9.892 MeV ) | 1.556 (b) | 755.8 (μb) | |||
17 | (n,3n) | ( E-thr = 18.01 MeV ) | − | 87.18 (nb) | |||
22 | (n,na) | ( E-thr = 811.6 keV ) | 1.079 (mb) | 342.2 (nb) | |||
28 | (n,np) | ( E-thr = 7.276 MeV ) | 3.479 (mb) | 629.0 (nb) | |||
32 | (n,nd) | ( E-thr = 14.42 MeV ) | − | 2.571e-12 (b) | |||
102 | (n,γ) | 18.71 (b) | 18.71 (b) | 1.000 | 8.655 (b) | 2.525 (mb) | 55.08 (mb) |
103 | (n,p) | ( E-thr = 1.386 MeV ) | 12.90 (mb) | 13.55 (μb) | |||
104 | (n,d) | ( E-thr = 4.949 MeV ) | 570.2 (μb) | 132.1 (nb) | |||
105 | (n,t) | ( E-thr = 8.188 MeV ) | 1.792 (μb) | 4.366 (nb) | |||
106 | (n,He-3) | ( E-thr = 4.757 MeV ) | 162.9e-12 (b) | 14.70e-12 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 439.9 (μb) | 6.223 (mb) | 33.33 (μb) |
These cross sections are calculated from JENDL-3.2 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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