MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 5.592 (b) | 6.291 (b) | 1.125 | − | 4.849 (b) | 5.934 (b) |
2 | (n,elastic) | 5.396 (b) | 6.090 (b) | 1.129 | − | 2.790 (b) | 4.945 (b) |
4 | (n,inelastic) | ( E-thr = 981.3 keV ) | 358.1 (mb) | 984.6 (mb) | |||
16 | (n,2n) | ( E-thr = 8.106 MeV ) | 1.701 (b) | 3.211 (mb) | |||
17 | (n,3n) | ( E-thr = 14.08 MeV ) | − | 2.668 (μb) | |||
22 | (n,na) | ( E-thr = 4.305 MeV ) | 49.75 (nb) | 119.3e-12 (b) | |||
28 | (n,np) | ( E-thr = 10.56 MeV ) | 801.9 (nb) | 9.234 (nb) | |||
32 | (n,nd) | ( E-thr = 16.15 MeV ) | − | 78.13e-15 (b) | |||
102 | (n,γ) | 195.1 (mb) | 195.2 (mb) | 1.001 | 168.4 (mb) | 1.061 (mb) | 1.667 (mb) |
103 | (n,p) | ( E-thr = 4.762 MeV ) | 2.595 (mb) | 752.0 (nb) | |||
104 | (n,d) | ( E-thr = 8.322 MeV ) | 11.60 (μb) | 10.64 (nb) | |||
105 | (n,t) | ( E-thr = 9.844 MeV ) | 25.69 (nb) | 257.7e-12 (b) | |||
106 | (n,He-3) | ( E-thr = 11.99 MeV ) | 0.000 (b) | 289.9e-21 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 379.4 (nb) | 24.48 (μb) | 19.72 (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 :
|