MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 7.924 (b) | 8.653 (b) | 1.092 | − | 4.338 (b) | 5.664 (b) |
2 | (n,elastic) | 5.685 (b) | 6.414 (b) | 1.128 | − | 2.829 (b) | 4.714 (b) |
4 | (n,inelastic) | ( E-thr = 270.0 keV ) | 112.1 (mb) | 925.0 (mb) | |||
16 | (n,2n) | ( E-thr = 6.810 MeV ) | 1.380 (b) | 8.597 (mb) | |||
17 | (n,3n) | ( E-thr = 15.54 MeV ) | − | 1.269 (μb) | |||
22 | (n,na) | ( E-thr = 3.372 MeV ) | 415.6 (μb) | 91.64 (nb) | |||
28 | (n,np) | ( E-thr = 9.692 MeV ) | 87.95 (μb) | 44.59 (nb) | |||
32 | (n,nd) | ( E-thr = 13.98 MeV ) | 0.000 (b) | 323.6e-12 (b) | |||
33 | (n,nt) | ( E-thr = 15.76 MeV ) | − | 1.482e-12 (b) | |||
102 | (n,γ) | 2.239 (b) | 2.238 (b) | 1.000 | 18.20 (b) | 1.000 (mb) | 14.79 (mb) |
103 | (n,p) | ( E-thr = 2.130 MeV ) | 10.75 (mb) | 7.671 (μb) | |||
104 | (n,d) | ( E-thr = 7.357 MeV ) | 570.6 (μb) | 123.7 (nb) | |||
105 | (n,t) | ( E-thr = 7.725 MeV ) | 73.61 (μb) | 26.58 (nb) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 253.1 (μb) | 3.450 (mb) | 24.28 (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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