Article ID Journal Published Year Pages File Type
8070171 Annals of Nuclear Energy 2013 16 Pages PDF
Abstract
► In this paper, the changes of the thermo-neutronic parameters of a VVER 1000 reactor were studied during the first cycle. ► The coupling of neutronic and thermo-hydraulic codes was utilized. ► A computational program (WERL code) was designed to calculate the temperature distribution of the reactor core. ► To estimate the concentration of the released gaseous fission products, the Weisman model was used. ► The results of this study enjoyed the desirable accuracy.
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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