Assessment of TASS/SMR code for a loss of coolant flow transient using results of integral type test facility

Many countries have taken an interest in small and medium sized nuclear power plants. SMART, which was developed by Korea Atomic Energy Research Institute (KAERI), is a small sized integral type pressurized water reactor with a rated thermal power of 330 MW. In order to analyze thermal hydraulic characteristics of the SMART design, the TASS/SMR code has been developed. The code was validated using the results of basic and separate effect tests including small scale experiments for the SMART special components. To enhance an analysis capability of the TASS/SMR code for an integral type PWR, the KAERI has constructed the VISTA-ITL facility, and several integral effect tests have been performed at the VISTA-ITL facility. The TASS/SMR code is validated using the results of a loss of coolant flow transient, which is one of the integral effect tests performed at the VISTA-ITL. According to the evaluation results, the code predicts well the overall thermal hydraulic behaviors including the system pressure, fluid temperature, and mass flow rate. The main coolant pump model is important in order to simulate well the primary coolant flow behavior at an early transient.