MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 103.5 (b) | 105.9 (b) | 1.023 | − | 3.841 (b) | 4.942 (b) |
2 | (n,elastic) | 18.52 (b) | 20.90 (b) | 1.128 | − | 2.550 (b) | 3.902 (b) |
4 | (n,inelastic) | ( E-thr = 566.5 keV ) | 349.9 (mb) | 1.020 (b) | |||
16 | (n,2n) | ( E-thr = 11.31 MeV ) | 824.9 (mb) | 154.6 (μb) | |||
17 | (n,3n) | ( E-thr = 19.45 MeV ) | − | 226.3e-12 (b) | |||
22 | (n,na) | ( E-thr = 5.166 MeV ) | 12.87 (mb) | 3.775 (μb) | |||
28 | (n,np) | ( E-thr = 9.645 MeV ) | 11.20 (mb) | 1.982 (μb) | |||
102 | (n,γ) | 85.02 (b) | 85.02 (b) | 1.000 | 41.01 (b) | 1.023 (mb) | 17.46 (mb) |
103 | (n,p) | ( E-thr = 2.215 MeV ) | 73.36 (mb) | 606.4 (μb) | |||
104 | (n,d) | ( E-thr = 7.305 MeV ) | 146.2 (μb) | 57.84 (nb) | |||
105 | (n,t) | ( E-thr = 11.42 MeV ) | 13.03 (nb) | 1.541 (nb) | |||
106 | (n,He-3) | ( E-thr = 8.808 MeV ) | 480.7e-12 (b) | 3.999e-12 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 5.789 (mb) | 17.19 (mb) | 253.0 (μb) |
111 | (n,2p) | ( E-thr = 10.05 MeV ) | 822.1e-12 (b) | 175.8e-12 (b) |
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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