MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 10.10 (b) | 10.58 (b) | 1.047 | − | 2.316 (b) | 3.259 (b) |
2 | (n,elastic) | 3.682 (b) | 4.157 (b) | 1.129 | − | 991.9 (mb) | 2.621 (b) |
4 | (n,inelastic) | ( E-thr = 162.8 keV ) | 749.7 (mb) | 631.7 (mb) | |||
16 | (n,2n) | ( E-thr = 8.311 MeV ) | 426.5 (mb) | 104.9 (μb) | |||
17 | (n,3n) | ( E-thr = 19.48 MeV ) | − | 3.080e-12 (b) | |||
22 | (n,na) | ( E-thr = 8.189 MeV ) | 490.1 (μb) | 129.4 (nb) | |||
28 | (n,np) | ( E-thr = 10.58 MeV ) | 30.24 (mb) | 5.046 (μb) | |||
102 | (n,γ) | 6.419 (b) | 6.422 (b) | 1.001 | 2.923 (b) | 358.0 (μb) | 2.716 (mb) |
103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 24.83 (mb) | 78.03 (mb) | 2.655 (mb) |
104 | (n,d) | ( E-thr = 8.306 MeV ) | 1.141 (mb) | 219.1 (nb) | |||
105 | (n,t) | ( E-thr = 10.98 MeV ) | 1.116 (μb) | 1.223 (nb) | |||
106 | (n,He-3) | ( E-thr = 9.731 MeV ) | 35.34 (nb) | 93.56e-12 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 4.497 (mb) | 38.98 (mb) | 348.0 (μb) |
111 | (n,2p) | ( E-thr = 8.478 MeV ) | 95.53 (μb) | 24.67 (nb) |
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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