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Fuzzy finite element analysis of multi–group neutron diffusion equation with imprecise parameters

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In this paper, multi–group neutron diffusion equation with imprecise parameters has been solved using proposed fuzzy finite element method. The proposed method is demonstrated by investigating the neutron fluxes viz. thermal and fast group fluxes of a benchmark problem ANL–BSS–6–A2. Various parameters such as thermal conductivity, diffusion, group fission and neutron interaction constants are taken as fuzzy and the uncertain solutions viz. thermal and fast group fluxes are studied in detail. Finally, obtained results are compared with existing ones in special cases and sensitivity of uncertain parameters is analysed.

Keywords: fuzzy FEA, finite element analysis, alpha–cut, neutron diffusion equation, neutron flux, nuclear energy, nuclear power, imprecise parameters, thermal conductivity, group fission, neutron interaction constants, fuzzy logic

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