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피동충수용 혼합형 안전주입탱크의 압력평형에 관한 이론적 해석 및 시험적 연구
류성욱(Sung Uk Ryu),유효봉(Hyobong Ryu),변선준(Sun-Joon Byun),전우진(Woo-Jin Jeon),박현식(Hyun-Sik Park),이성재(Sung-Jae Lee) 한국에너지학회 2015 한국에너지공학회 학술발표회 Vol.2015 No.11
피동충수용 혼합형 안전주입탱크는 한국원자력연구원에서 제안한 원자력 피동안전계통의 한 종류로, 안전주입탱크의 상부와 가압기를 연결하여 모든 운전압력 조건에서 냉각수 주입이 가능하도록 개선한 시스템이다. 본 연구에서는 피동충수용 혼합형 안전주입탱크, 가압기와 원자력압력용기에 대한 압력 네트워크를 통해 피동충수용 혼합형 안전주입탱크와 가압기의 압력이 평형이 되는 조건을 이론적으로 도출하였으며, 개별효과시험장치를 이용하여 안전주입탱크에서 발생하는 다양한 열수력 현상(증기응축 및 열혼합 현상)들을 파악하였다. The Hybrid Safety Injection Tank is a passive safety injection system that enables the safety injection water to be injected into the reactor pressure vessel throughout all operating pressures by connecting the top of the SIT and the pressurizer(PZR). In this study, the condition for balancing the pressure between the Hybrid SIT and PZR was derived theoretically. The pressure balancing condition was set at the point where the velocity of the Hybrid SIT coolant injected into the Direct Vessel Injection(DVI) line was at or above zero. If the condition was derived from a pressure network for the Hybrid SIT, pressurizer, and reactor pressure vessel, the pressure difference between the pressurizer and SIT is less than 0.07 MPa.
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.