Article ID Journal Published Year Pages File Type
8070221 Annals of Nuclear Energy 2013 9 Pages PDF
Abstract
► Simulation of one-sixth of VVER reactor core by MCNP4C code based on symmetry of it by information of FSAR. ► Calculation of neutron flux and Keff of VVER reactor and transferring the results as inputs to WIMS-D4 code. ► Transferring the cross sections calculated by WIMS-D4 as inputs to CITATION code by assessing the genetic responses. ► Defining a mathematical model and developing a new method based on genetic algorithm for core fuel loading pattern. ► Determination of the best status of interchanging the fuel assemblies for acceptable responses to attain maximum energy.
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Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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