MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 83.67 (b) | 84.17 (b) | 1.006 | − | 4.974 (b) | 5.881 (b) |
2 | (n,elastic) | 3.615 (b) | 4.081 (b) | 1.129 | − | 3.091 (b) | 4.583 (b) |
4 | (n,inelastic) | ( E-thr = 150.9 keV ) | 211.4 (mb) | 1.264 (b) | |||
16 | (n,2n) | ( E-thr = 8.697 MeV ) | 1.670 (b) | 2.105 (mb) | |||
17 | (n,3n) | ( E-thr = 15.21 MeV ) | − | 2.323 (μb) | |||
22 | (n,na) | ( E-thr = 3.193 MeV ) | 6.376 (μb) | 4.801 (nb) | |||
28 | (n,np) | ( E-thr = 7.454 MeV ) | 396.4 (μb) | 114.0 (nb) | |||
32 | (n,nd) | ( E-thr = 13.61 MeV ) | 0.000 (b) | 102.9e-12 (b) | |||
33 | (n,nt) | ( E-thr = 13.51 MeV ) | 0.000 (b) | 27.81e-12 (b) | |||
102 | (n,γ) | 80.03 (b) | 80.07 (b) | 1.001 | 77.81 (b) | 1.001 (mb) | 31.49 (mb) |
103 | (n,p) | ( E-thr = 1.479 MeV ) | 1.638 (mb) | 674.0 (nb) | |||
104 | (n,d) | ( E-thr = 5.126 MeV ) | 211.9 (μb) | 86.33 (nb) | |||
105 | (n,t) | ( E-thr = 7.375 MeV ) | 4.455 (μb) | 13.26 (nb) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 2.627 (μb) | 858.1 (μb) | 301.6 (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 :
|