The Prediction of TASS/SMR-S Code for the Natural Circulation at VISTA Facility

The Transients And Setpoint Simulation/System integrated Modular Reactor-S (TASS/SMR-S) code that was developed by the Korea Atomic Energy Research Institute (KAERI) is used to calculate the performance evaluation and safety analysis for System Integrated Modular Advanced Reactor (SMART). TASS/SMR-S code is applied an analysis of Design Basis Accident (DBA) that include transient phenomena of SMART and Small Break loss of Coolant Accident (SBLOCA). So far, TASS/SMR-S code was validated for the main issues. In this study, TASS/SMR-S is validated by using the natural circulation experiment for power variation that is one of thermal-hydraulic experiments using Verification by Integral Simulation of Transients and Accidents (VISTA)