MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 19.24 (b) | 19.86 (b) | 1.032 | − | 3.225 (b) | 4.198 (b) |
2 | (n,elastic) | 4.834 (b) | 5.454 (b) | 1.128 | − | 1.663 (b) | 3.071 (b) |
4 | (n,inelastic) | ( E-thr = 13.48 keV ) | 407.1 (mb) | 1.109 (b) | |||
16 | (n,2n) | ( E-thr = 6.877 MeV ) | 1.123 (b) | 2.274 (mb) | |||
17 | (n,3n) | ( E-thr = 17.77 MeV ) | − | 23.89 (nb) | |||
22 | (n,na) | ( E-thr = 5.375 MeV ) | 627.3 (μb) | 140.5 (nb) | |||
28 | (n,np) | ( E-thr = 10.13 MeV ) | 736.6 (μb) | 194.6 (nb) | |||
32 | (n,nd) | ( E-thr = 14.49 MeV ) | − | 206.4e-12 (b) | |||
102 | (n,γ) | 14.40 (b) | 14.41 (b) | 1.000 | 62.25 (b) | 761.4 (μb) | 13.75 (mb) |
103 | (n,p) | ( E-thr = 794.4 keV ) | 18.91 (mb) | 166.3 (μb) | |||
104 | (n,d) | ( E-thr = 7.877 MeV ) | 2.479 (mb) | 491.9 (nb) | |||
105 | (n,t) | ( E-thr = 8.144 MeV ) | 240.8 (μb) | 48.98 (nb) | |||
106 | (n,He-3) | ( E-thr = 10.97 MeV ) | 139.9e-15 (b) | 3.102e-12 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 2.696 (mb) | 7.852 (mb) | 224.3 (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 :
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