MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 21.22 (b) | 21.77 (b) | 1.026 | − | 4.638 (b) | 5.516 (b) |
2 | (n,elastic) | 3.776 (b) | 4.263 (b) | 1.129 | − | 2.932 (b) | 3.794 (b) |
4 | (n,inelastic) | ( E-thr = 10.79 keV ) | 158.4 (mb) | 1.628 (b) | |||
16 | (n,2n) | ( E-thr = 6.525 MeV ) | 1.541 (b) | 9.826 (mb) | |||
17 | (n,3n) | ( E-thr = 15.57 MeV ) | − | 1.766 (μb) | |||
22 | (n,na) | ( E-thr = 4.371 MeV ) | 1.144 (μb) | 1.705 (nb) | |||
28 | (n,np) | ( E-thr = 7.144 MeV ) | 628.3 (μb) | 127.2 (nb) | |||
32 | (n,nd) | ( E-thr = 10.81 MeV ) | 60.28e-15 (b) | 5.571 (nb) | |||
33 | (n,nt) | ( E-thr = 13.47 MeV ) | 0.000 (b) | 30.41e-12 (b) | |||
102 | (n,γ) | 17.41 (b) | 17.42 (b) | 1.001 | 155.7 (b) | 1.001 (mb) | 80.44 (mb) |
103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 74.14 (μb) | 3.182 (mb) | 4.027 (μb) |
104 | (n,d) | ( E-thr = 4.815 MeV ) | 804.0 (μb) | 161.1 (nb) | |||
105 | (n,t) | ( E-thr = 4.579 MeV ) | 67.63 (μb) | 22.84 (nb) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 3.491 (μb) | 1.498 (mb) | 489.1 (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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