Psb-Vver Test Tesisi Deneylerinin Termal Hidrolik Olarak Modellenmesiyle Relap5 Kodunun Doğrulanması

Abstract

In this work loss of coolant accident analysis was done by simulating an experiment which assumes a small break in cold leg between main circulation pump and pressure vessel. Behaviour of pressure, temperature, power, break mass, accumulator level parameters were investigated for the accident scenario by dividing hexagonal reactor core into different numbers of thermal hydraulic sub-channels. Lateral flow was provided by defining cross-flow between thermal hydraulic channels, effect on peak clad temperature, accumulator ve low pressure emergency core cooling system actuation time, mass flow rate parameters by checking against non-mixing flow situation were observed. Code validation was performed by comparing PSB-VVER test facility experimental results with results obtained from processing core nodalization modification and calculations into RELAP5 MOD 3.5 input file.