MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 5.051 (b) | 5.661 (b) | 1.121 | − | 4.316 (b) | 5.737 (b) |
2 | (n,elastic) | 4.733 (b) | 5.344 (b) | 1.129 | − | 2.295 (b) | 4.246 (b) |
4 | (n,inelastic) | ( E-thr = 105.0 keV ) | 563.6 (mb) | 1.423 (b) | |||
16 | (n,2n) | ( E-thr = 9.652 MeV ) | 1.440 (b) | 829.7 (μb) | |||
17 | (n,3n) | ( E-thr = 16.81 MeV ) | − | 93.57 (nb) | |||
22 | (n,na) | ( E-thr = 3.260 MeV ) | 201.5 (μb) | 71.82 (nb) | |||
28 | (n,np) | ( E-thr = 9.435 MeV ) | 308.8 (μb) | 132.9 (nb) | |||
32 | (n,nd) | ( E-thr = 16.24 MeV ) | − | 205.9e-15 (b) | |||
102 | (n,γ) | 317.1 (mb) | 317.2 (mb) | 1.000 | 7.801 (b) | 972.5 (μb) | 65.35 (mb) |
103 | (n,p) | ( E-thr = 2.785 MeV ) | 12.95 (mb) | 8.201 (μb) | |||
104 | (n,d) | ( E-thr = 7.189 MeV ) | 633.2 (μb) | 139.0 (nb) | |||
105 | (n,t) | ( E-thr = 9.925 MeV ) | 53.90 (nb) | 627.2e-12 (b) | |||
106 | (n,He-3) | ( E-thr = 8.756 MeV ) | 68.30e-15 (b) | 30.19e-15 (b) | |||
107 | (n,a) | 2.568e-15 (b) | 2.597e-15 (b) | 1.011 | 124.1 (μb) | 4.461 (mb) | 6.829 (μb) |
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 :
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