MARS-KS 코드를 이용한 파단크기별 SMART 종합시험장치의 안전계통 특성 검증

SMART, an integral type small modular reactor, was developed in KAERI and received its design certificate in 2012. The reactor is characterized by enhanced safety by removal of large diameter pipes and adoption of passive safety systems. An integral test facility for SMART was built in KAERI and a series of experiments have been performed to explore the thermal hydraulic phenomena that accompany the operation of safety systems. In parallel to the experiments, intense efforts have been made to simulate using a system code, MARK-KS. The code is devoted to calculate transients of nuclear power plant systems under postulated accidents. In this paper, for two representative accident scenarios with different pipe break sizes, we compared the calculation results with the experimental results and obtained good predictions.