MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 12.80 (b) | 14.28 (b) | 1.116 | − | 5.311 (b) | 6.940 (b) |
2 | (n,elastic) | 11.49 (b) | 12.97 (b) | 1.129 | − | 2.590 (b) | 4.217 (b) |
4 | (n,inelastic) | ( E-thr = 79.20 keV ) | 595.4 (mb) | 2.653 (b) | |||
16 | (n,2n) | ( E-thr = 8.067 MeV ) | 2.121 (b) | 4.621 (mb) | |||
17 | (n,3n) | ( E-thr = 14.72 MeV ) | − | 3.865 (μb) | |||
22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 12.18 (nb) | 89.07 (μb) | 28.97 (nb) |
28 | (n,np) | ( E-thr = 7.377 MeV ) | 57.57 (μb) | 38.63 (nb) | |||
32 | (n,nd) | ( E-thr = 12.67 MeV ) | 0.000 (b) | 12.06e-12 (b) | |||
102 | (n,γ) | 1.313 (b) | 1.314 (b) | 1.001 | 27.16 (b) | 784.3 (μb) | 65.22 (mb) |
103 | (n,p) | ( E-thr = 1.104 MeV ) | 6.143 (mb) | 2.986 (μb) | |||
104 | (n,d) | ( E-thr = 5.139 MeV ) | 642.0 (μb) | 161.2 (nb) | |||
105 | (n,t) | ( E-thr = 6.375 MeV ) | 13.03 (μb) | 7.967 (nb) | |||
106 | (n,He-3) | ( E-thr = 6.041 MeV ) | 0.000 (b) | 111.6e-15 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 20.11 (μb) | 977.2 (μb) | 1.453 (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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