چکیده مقاله
In this study, we have reformulated the AFEN method for diffusion equations and implemented in a version of the AFEN method code MGHANSP3 for rectangular z geometry For increasing the speed of calculations, the coarse group rebalancing CGR method has been utilized Finally, we developed a computer code, named SDANM, using C# programming language This code takes few group macroscopic cross sections and calculates the effective multiplication factor, reactivity, multi groups fluxes, power density distributions and power peaking factor in reactor cores with square geometry The solution accuracy is examined for IAEA benchmark problem The numerical results illustrate that the SDANM code is an accurate code for calculating multiplication factor and power density distributions
کلیدواژهها
نویسندگان
Mohammad Hassan Jalili Bahabadi
Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran
Ali Pazirandeh
Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran
Mitra Athari
Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran
شیوه ارجاع
Jalili Bahabadi, Mohammad Hassan and Pazirandeh, Ali and Athari, Mitra,1394,Development of a computer code for neutronic modeling of reactor core with rectangular fuel assembly,International Conference on New Research Findings in Electrical Engineering and Computer Science,Tehran
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