MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 5.332 (b) | 5.962 (b) | 1.118 | − | 4.213 (b) | 5.935 (b) |
2 | (n,elastic) | 4.885 (b) | 5.515 (b) | 1.129 | − | 2.293 (b) | 4.676 (b) |
4 | (n,inelastic) | ( E-thr = 786.4 keV ) | 503.7 (mb) | 1.234 (b) | |||
16 | (n,2n) | ( E-thr = 9.251 MeV ) | 1.384 (b) | 1.124 (mb) | |||
17 | (n,3n) | ( E-thr = 16.70 MeV ) | − | 117.3 (nb) | |||
22 | (n,na) | ( E-thr = 2.791 MeV ) | 893.2 (μb) | 209.9 (nb) | |||
28 | (n,np) | ( E-thr = 9.395 MeV ) | 634.1 (μb) | 219.2 (nb) | |||
32 | (n,nd) | ( E-thr = 15.73 MeV ) | − | 4.942e-12 (b) | |||
102 | (n,γ) | 447.0 (mb) | 447.4 (mb) | 1.001 | 17.52 (b) | 884.6 (μb) | 22.64 (mb) |
103 | (n,p) | ( E-thr = 2.430 MeV ) | 19.02 (mb) | 18.12 (μb) | |||
104 | (n,d) | ( E-thr = 7.147 MeV ) | 3.189 (mb) | 615.4 (nb) | |||
105 | (n,t) | ( E-thr = 9.402 MeV ) | 6.624 (μb) | 6.591 (nb) | |||
106 | (n,He-3) | ( E-thr = 8.472 MeV ) | 1.829e-12 (b) | 2.223e-12 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 690.0 (μb) | 7.841 (mb) | 46.03 (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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