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SMART-ITL 1 계열 피동안전계통을 이용한 안전주입배관 파단 소형냉각재상실사고 모의에 대한 실험적 연구
류성욱(Sung Uk Ryu),배황(Hwang Bae),유효봉(Hyo Bong Ryu),변선준(Sun Joon Byun),김우식(Woo Shik Kim),신용철(Yong-Cheol Shin),이성재(Sung-Jae Yi),박현식(Hyun-Sik Park) 대한기계학회 2016 大韓機械學會論文集B Vol.40 No.3
노심보충탱크(Core Makeup Tank, CMT), 안전주입탱크(SafetyInjection Tank, SIT)와 자동감압계통(Auto Depressurization System, ADS)로 구성된 1 계열의 SMART 피동안전주입계통의 주입특성을 파악하기 위한 소형냉각재상실사고(SBLOCA) 모의에 대한 실험적 연구가 수행되었다. SBLOCA 모의시험은 0.4 인치 안전주입수 배관파단에 대해 수행되었으며, 정상상태 조건은 실험요건서에 제시된 시험 초기 조건을 만족시키도록 746초 동안 운전되었다. 노심 출력 및 안전주입 유량 등의 경계 조건도 적절히 모의되었으며, 안전주입계통 배관에서의 파단, 히터 트립 및 잔열곡선 인가, 원자로냉각재펌프 관성서행(Coastdown), 급수 중단, CMT 및 SIT의 주입, ADS #1 개방이 SBLOCA 시나리오에 따라 적절히 모의되었다. 노심지지원통 내부의 액체환산수위는 파단 초반에 감소하다가 CMT와 SIT가 주입되면서 서서히 회복되었으며, 피동안전주입계통의 주입유량이 노심 수위를 회복하기에 충분한 것으로 판단할 수 있다. An experimental study of the thermal-hydraulic characteristics of passive safety systems (PSSs) was conducted using a system-integrated modular advanced reactor-integral test loop (SMART-ITL). The present passive safety injection system for the SMART-ITL consists of one train with the core makeup tank (CMT), the safety injection tank, and the automatic depressurization system. The objective of this study is to investigate the injection effect of the PSS on the small-break loss-of-coolant accident (SBLOCA) scenario for a 0.4 inch line break in the safety-injection system (SIS). The steady-state condition was maintained for 746 seconds before the break. When the major parameters of the target value and test results were compared, most of the thermal-hydraulic parameters agreed closely with each other. The water level of the reactor pressure vessel (RPV) was maintained higher than that of the fuel assembly plate during the transient, for the present CMT and safety injection tank (SIT) flow rate conditions. It can be seen that the capability of an emergency core cooling system is sufficient during the transient with SMART passive SISs.
류성욱(Sung Uk Ryu),전병국(Byung Gook Jeon),어동진(Dong-Jin Euh) 대한기계학회 2016 대한기계학회 춘추학술대회 Vol.2016 No.12
Despite a few previous studies, researches on the passive safety injection systems such as core makeup tank and hybrid safety injection tank in the nuclear power plants have so far been limited to using analytical and numerical methods. The overall thermal-hydraulic phenomena occurred in the passive safety injection tanks must be examined experimentally not only to verify the validity of the system design but also to evaluate the predicting capability of system codes. Recently, a high precision experiment facility for passive safety injection systems was constructed at KAERI. This research was done with the purpose of examining various thermal-hydraulic phenomena such as steam condensation, thermal mixing and coolant thermal stratification that occur in the passive safety injection tanks.