MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 12.24 (b) | 13.65 (b) | 1.116 | − | 3.842 (b) | 5.699 (b) |
2 | (n,elastic) | 10.98 (b) | 12.39 (b) | 1.129 | − | 2.138 (b) | 4.998 (b) |
4 | (n,inelastic) | ( E-thr = 1.218 MeV ) | 360.3 (mb) | 689.3 (mb) | |||
16 | (n,2n) | ( E-thr = 7.283 MeV ) | 1.304 (b) | 2.294 (mb) | |||
17 | (n,3n) | ( E-thr = 19.40 MeV ) | − | 703.3e-12 (b) | |||
22 | (n,na) | ( E-thr = 5.513 MeV ) | 3.772 (μb) | 2.126 (nb) | |||
28 | (n,np) | ( E-thr = 8.805 MeV ) | 2.729 (mb) | 673.9 (nb) | |||
32 | (n,nd) | ( E-thr = 13.49 MeV ) | 0.000 (b) | 2.898 (nb) | |||
102 | (n,γ) | 1.261 (b) | 1.262 (b) | 1.000 | 5.726 (b) | 1.002 (mb) | 9.070 (mb) |
103 | (n,p) | ( E-thr = 769.0 keV ) | 27.38 (mb) | 100.2 (μb) | |||
104 | (n,d) | ( E-thr = 6.556 MeV ) | 2.356 (mb) | 641.4 (nb) | |||
105 | (n,t) | ( E-thr = 7.165 MeV ) | 83.94 (μb) | 18.22 (nb) | |||
106 | (n,He-3) | ( E-thr = 8.652 MeV ) | 627.1e-12 (b) | 7.323e-12 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 1.214 (mb) | 7.865 (mb) | 136.1 (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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