MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 1.854 (kb) | 2.221 (kb) | 1.198 | − | 5.028 (b) | 6.575 (b) |
2 | (n,elastic) | 6.600 (b) | 7.417 (b) | 1.124 | − | 3.267 (b) | 4.390 (b) |
4 | (n,inelastic) | ( E-thr = 68.65 keV ) | 213.4 (mb) | 1.655 (b) | |||
16 | (n,2n) | ( E-thr = 6.481 MeV ) | 1.541 (b) | 10.94 (mb) | |||
17 | (n,3n) | ( E-thr = 15.09 MeV ) | − | 2.990 (μb) | |||
22 | (n,na) | ( E-thr = 601.8 keV ) | 55.25 (μb) | 20.18 (nb) | |||
28 | (n,np) | ( E-thr = 6.505 MeV ) | 279.1 (μb) | 77.72 (nb) | |||
32 | (n,nd) | ( E-thr = 10.09 MeV ) | 7.643e-12 (b) | 5.531 (nb) | |||
33 | (n,nt) | ( E-thr = 12.18 MeV ) | 0.000 (b) | 79.64e-12 (b) | |||
102 | (n,γ) | 1.847 (kb) | 2.213 (kb) | 1.198 | 1.176 (kb) | 1.001 (mb) | 516.1 (mb) |
103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 44.74 (μb) | 3.793 (mb) | 2.704 (μb) |
104 | (n,d) | ( E-thr = 4.180 MeV ) | 939.6 (μb) | 211.3 (nb) | |||
105 | (n,t) | ( E-thr = 3.865 MeV ) | 89.26 (μb) | 31.50 (nb) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 14.55 (μb) | 1.394 (mb) | 1.040 (μb) |
These cross sections are calculated from JENDL-3.3 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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