MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 10.42 (b) | 11.48 (b) | 1.101 | − | 3.193 (b) | 3.755 (b) |
2 | (n,elastic) | 8.223 (b) | 9.279 (b) | 1.128 | − | 1.593 (b) | 2.926 (b) |
4 | (n,inelastic) | ( E-thr = 323.4 keV ) | 720.3 (mb) | 809.0 (mb) | |||
16 | (n,2n) | ( E-thr = 10.46 MeV ) | 790.8 (mb) | 186.2 (μb) | |||
22 | (n,na) | ( E-thr = 4.548 MeV ) | 1.833 (mb) | 856.8 (nb) | |||
28 | (n,np) | ( E-thr = 6.704 MeV ) | 17.07 (mb) | 21.90 (μb) | |||
32 | (n,nd) | ( E-thr = 14.79 MeV ) | − | 5.008 (nb) | |||
102 | (n,γ) | 2.201 (b) | 2.201 (b) | 1.000 | 18.22 (b) | 772.3 (μb) | 16.92 (mb) |
103 | (n,p) | ( E-thr = 126.1 keV ) | 39.37 (mb) | 2.612 (mb) | |||
104 | (n,d) | ( E-thr = 4.447 MeV ) | 6.081 (mb) | 4.960 (μb) | |||
105 | (n,t) | ( E-thr = 8.446 MeV ) | 358.6 (μb) | 74.16 (nb) | |||
106 | (n,He-3) | ( E-thr = 9.010 MeV ) | 11.15 (nb) | 48.01e-12 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 6.221 (mb) | 23.34 (mb) | 437.6 (μb) |
111 | (n,2p) | ( E-thr = 10.56 MeV ) | 323.6e-12 (b) | 65.79e-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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