MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 56.46 (b) | 57.40 (b) | 1.017 | − | 3.493 (b) | 4.894 (b) |
2 | (n,elastic) | 6.342 (b) | 7.159 (b) | 1.129 | − | 1.801 (b) | 3.079 (b) |
4 | (n,inelastic) | ( E-thr = 96.99 keV ) | 404.2 (mb) | 1.765 (b) | |||
16 | (n,2n) | ( E-thr = 7.052 MeV ) | 1.263 (b) | 3.138 (mb) | |||
17 | (n,3n) | ( E-thr = 17.68 MeV ) | − | 31.66 (nb) | |||
22 | (n,na) | ( E-thr = 6.569 MeV ) | 20.33 (μb) | 12.96 (nb) | |||
28 | (n,np) | ( E-thr = 10.52 MeV ) | 91.20 (μb) | 81.54 (nb) | |||
32 | (n,nd) | ( E-thr = 15.33 MeV ) | − | 34.15e-12 (b) | |||
102 | (n,γ) | 50.02 (b) | 50.04 (b) | 1.001 | 108.7 (b) | 1.269 (mb) | 45.36 (mb) |
103 | (n,p) | ( E-thr = 1.518 MeV ) | 21.88 (mb) | 46.55 (μb) | |||
104 | (n,d) | ( E-thr = 8.269 MeV ) | 1.205 (mb) | 221.6 (nb) | |||
105 | (n,t) | ( E-thr = 8.993 MeV ) | 6.047 (μb) | 1.904 (nb) | |||
106 | (n,He-3) | ( E-thr = 11.71 MeV ) | 0.000 (b) | 215.9e-15 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 119.5 (μb) | 1.060 (mb) | 7.754 (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 :
|