عنوان مقاله [English]
نویسندگان [English]چکیده [English]
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.