MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 5.847 (b) | 6.601 (b) | 1.129 | − | 3.874 (b) | 5.753 (b) |
2 | (n,elastic) | 5.837 (b) | 6.590 (b) | 1.129 | − | 2.156 (b) | 4.699 (b) |
4 | (n,inelastic) | ( E-thr = 841.0 keV ) | 331.2 (mb) | 1.046 (b) | |||
16 | (n,2n) | ( E-thr = 7.891 MeV ) | 1.381 (b) | 3.519 (mb) | |||
17 | (n,3n) | ( E-thr = 14.32 MeV ) | − | 1.851 (μb) | |||
22 | (n,na) | ( E-thr = 5.158 MeV ) | 18.97 (μb) | 7.467 (nb) | |||
28 | (n,np) | ( E-thr = 11.65 MeV ) | 204.2 (nb) | 11.92 (nb) | |||
32 | (n,nd) | ( E-thr = 16.65 MeV ) | − | 381.6e-15 (b) | |||
102 | (n,γ) | 10.10 (mb) | 10.11 (mb) | 1.000 | 86.01 (mb) | 599.0 (μb) | 3.517 (mb) |
103 | (n,p) | ( E-thr = 5.863 MeV ) | 4.201 (mb) | 1.140 (μb) | |||
104 | (n,d) | ( E-thr = 9.398 MeV ) | 117.8 (μb) | 36.37 (nb) | |||
105 | (n,t) | ( E-thr = 10.33 MeV ) | 73.97 (nb) | 838.3e-12 (b) | |||
106 | (n,He-3) | ( E-thr = 13.26 MeV ) | 0.000 (b) | 3.803e-18 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 8.153 (μb) | 286.3 (μb) | 326.5 (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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