Numerical Modeling of VVER-1000 Coolant Channels in Transient Core Inlet Flowrate Condition
Document Type : Research Paper
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Abstract
Due to importance of nuclear reactors safety, numerical modeling of VVER-1000 coolant channels in transient core inlet flowrate is discussed. To do this, core of the Bushehr VVER-1000 reactor is divided into four channels. Then, termohydraulic parameters of each channel including coolant and fuel temperature distributions and pressure drop of channels is calculated. For these calculations, a program is developed by Fortran90 programming language. The obtained results from both program and RELAP5 code are compared. Good consistency of compared results verified the developed program.
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