MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 9.976 (b) | 11.15 (b) | 1.118 | − | 3.177 (b) | 4.171 (b) |
2 | (n,elastic) | 9.165 (b) | 10.34 (b) | 1.128 | − | 1.729 (b) | 3.386 (b) |
4 | (n,inelastic) | ( E-thr = 701.3 keV ) | 610.8 (mb) | 760.1 (mb) | |||
16 | (n,2n) | ( E-thr = 10.90 MeV ) | 782.2 (mb) | 175.5 (μb) | |||
17 | (n,3n) | ( E-thr = 18.42 MeV ) | − | 3.691 (nb) | |||
22 | (n,na) | ( E-thr = 5.071 MeV ) | 1.165 (mb) | 408.6 (nb) | |||
28 | (n,np) | ( E-thr = 9.867 MeV ) | 3.165 (mb) | 657.6 (nb) | |||
32 | (n,nd) | ( E-thr = 17.04 MeV ) | − | 2.331e-12 (b) | |||
102 | (n,γ) | 810.4 (mb) | 810.2 (mb) | 1.000 | 867.8 (mb) | 768.3 (μb) | 23.00 (mb) |
103 | (n,p) | ( E-thr = 3.255 MeV ) | 32.55 (mb) | 323.2 (μb) | |||
104 | (n,d) | ( E-thr = 7.611 MeV ) | 4.080 (mb) | 893.2 (nb) | |||
105 | (n,t) | ( E-thr = 10.70 MeV ) | 14.14 (μb) | 21.65 (nb) | |||
106 | (n,He-3) | ( E-thr = 10.02 MeV ) | 87.22e-12 (b) | 11.72e-12 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 1.578 (mb) | 13.64 (mb) | 87.67 (μb) |
These cross sections are calculated from JENDL-3.2 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 :
|