MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 131.5 (b) | 135.8 (b) | 1.032 | − | 4.842 (b) | 6.022 (b) |
2 | (n,elastic) | 31.81 (b) | 35.91 (b) | 1.129 | − | 2.748 (b) | 4.131 (b) |
4 | (n,inelastic) | ( E-thr = 80.80 keV ) | 200.6 (mb) | 1.855 (b) | |||
16 | (n,2n) | ( E-thr = 6.656 MeV ) | 1.874 (b) | 7.492 (mb) | |||
17 | (n,3n) | ( E-thr = 15.98 MeV ) | − | 821.8 (nb) | |||
22 | (n,na) | ( E-thr = 2.579 MeV ) | 38.23 (μb) | 13.23 (nb) | |||
28 | (n,np) | ( E-thr = 8.839 MeV ) | 258.0 (μb) | 148.2 (nb) | |||
32 | (n,nd) | ( E-thr = 13.15 MeV ) | 7.565e-21 (b) | 58.08e-12 (b) | |||
102 | (n,γ) | 99.68 (b) | 99.85 (b) | 1.002 | 909.2 (b) | 968.3 (μb) | 29.17 (mb) |
103 | (n,p) | ( E-thr = 190.0 keV ) | 20.03 (mb) | 24.60 (μb) | |||
104 | (n,d) | ( E-thr = 6.598 MeV ) | 813.7 (μb) | 174.4 (nb) | |||
105 | (n,t) | ( E-thr = 6.843 MeV ) | 9.698 (μb) | 4.704 (nb) | |||
106 | (n,He-3) | ( E-thr = 8.336 MeV ) | 23.86e-15 (b) | 65.93e-15 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 37.15 (μb) | 1.434 (mb) | 3.387 (μb) |
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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