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펌프 맥동하중에 대한 노심지지배럴 집합체의 음향-구조 연성해석
이장원,문종성,김정규,성기광,김현민,Lee, Jang Won,Moon, Jong Sung,Kim, Jung Gyu,Sung, Ki Kwang,Kim, Hyun Min 대한기계학회 2017 대한기계학회 논문집. Transactions of the KSME. C, 산업기술과 혁신 Vol.5 No.2
The reactor internals shall be secured in safety and structural integrity under various vibrational loading conditions. Thus, U.S. NRC, Regulatory Guide 1.20 requires the evaluation for the reactor internals due to acoustic induced vibration including the response to the reactor coolant pump pressure pulsation. This paper suggests a methodology to develop an analytical model of the core support barrel accounting for the fluid around the structure and to analyze the responses to the pump pulsation loads using acoustic structure interaction analysis. The analysis results were compared with those of US Palo Verde 1 CVAP and showed a good agreement. Thus, it is expected that the suggested methodology could be an efficient way to evaluate the response of the core support barrel to the pump pulsation loads. 원자로내부구조물은 다양한 진동하중조건에서 안전성과 건전성을 유지해야한다. 그러므로 미국원자력규제 위원회는 펌프 압력 맥동에 의한 진동을 포함하여 음향으로 유발되는 진동을 평가하기 위한 규제지침서 1.20을 제시하고 있다. 본 논문은 음향-구조 연성해석 기법을 사용하여 펌프 맥동 가진으로 인한 해석을 위해 노심지지배럴 주변의 유체와 구조의 연성을 고려하여 해석하는 방법론을 제안하였다. 해석결과는 미국 Palo Verde 1호기 종합진동평가 프로그램 발전소 시험결과와 잘 일치한다. 따라서 제안된 해석 방법론은 펌프 압력맥동에 대한 노심지지배럴의 구조응답을 평가하기 위한 효과적 방법으로 판단된다.
펌프 맥동하중에 대한 노심지지배럴 집합체의 음향 구조 연성해석
이장원(Jang Won Lee),문종성(Jong Sung Moon),김정규(Jung Gyu Kim),성기광(Ki Kwang Sung),김현민(Hyun Min Kim) 대한기계학회 2016 대한기계학회 춘추학술대회 Vol.2016 No.12
The reactor internals shall be secured in safety and structural integrity under various vibrational load conditions. Thus, U.S. NRC, Regulatory Guide 1.20 requires the evaluation for the reactor internals due to acoustic induced vibration including the response to the reactor coolant pump pressure pulsation. This paper suggests a methodology to develop an analytical model of the core support barrel accounting for the fluid and structures around the core support barrel and to analyze the responses to the pump pulsation loads using acoustic structure interaction analysis. The analysis result was compared to that Palo Verde CVAP and showed a good agreement. Thus, it is expected that the suggested methodology could be more efficient way to evaluate the core support barrel for the pump pulsation loads.
김철우(Cheol Woo Kim),문종성(Jong Sung Moon),김정규(Jung Gyu Kim),맹철수(Cheol Soo Maeng),성기광(Ki Kwang Sung),김현민(Hyun Min Kim) 대한기계학회 2016 대한기계학회 춘추학술대회 Vol.2016 No.12
Since the top mounted in-core instrumentation (TM-ICI) system has abilities to cope with severe accidents for simple configuration and no penetration of the reactor lower head, TM-ICI is under development in Korea. Therefore it needs development of the reactor internals for the TM-ICI. This paper introduces a finite element model of the reactor internals for TM-ICI and its dynamic characteristics for future structural response analyses.
김철우(Cheol-Woo Kim),문종성(Jong-Sung Moon),김정규(Jung-Gyu Kim),맹철수(Cheol-Soo Maeng),성기광(Ki Kwang Sung),김현민(Hyun-Min Kim) 대한기계학회 2018 대한기계학회 논문집. Transactions of the KSME. C, 산업기술과 혁신 Vol.6 No.1
상부탑재형 노내계측계통(top-mounted in-core instrumentation, TM-ICI)은 하부탑재형 노내계측계통(bottom mounted in-core instrumentation, BM-ICI)과 달리 원자로 하부 헤드에 관통부가 없고 구조가 단순하기 때문에 중대사고 발생 시 대처 능력을 향상시킬 수 있다. 국내 경수로 원전에서는 하부탑재형 노내계측계통을 채택하고 있기 때문에 중대사고 대응능력 향상을 위해 상부탑재형 노내계측계통 및 연계구조물의 설계를 개발 중에 있다. 본 논문에서는 현재 개발 중에 있는 TM-ICI의 연계 구조물인 원자로 내부구조물에 대한 유한요소 모델을 소개하고 동특성 해석 결과를 제시하였다. 본 논문에서 개발한 모델 및 결과는 다양한 하중에 대한 원자로내부구조물 응답해석에 적용할 수 있으며 상세 설계의 개선에 이용할 수 있을 것으로 기대된다. Since the top mounted in-core instrumentation (TM-ICI) system, which is different from the bottom mounted in-core instrumentation (BM-ICI), has simple configuration without penetration in the reactor lower head, it can improve the abilities to cope with severe accidents. Because domestic light water reactors have BM-ICI, TM-ICI is under development in Korea for improvement of ability to respond to severe accidents. This paper introduces a finite element model of the reactor internals for TM-ICI and its dynamic characteristics. The model and result in this paper are expected to be applied to response analysis for reactor internals of TM-ICI and to be used for improvement of detail design of TM-ICI component.
지반조건과 건물균열 효과에 따른 APR1400 원자로냉각재계통 지진응답 평가
김정용(Jung Yong Kim),전장환(Jang Hwan Jheon),성기광(Ki Kwang Sung),김현민(Hyun Min Kim) 대한기계학회 2016 대한기계학회 춘추학술대회 Vol.2016 No.12
Seismic analysis for the APR1400 Reactor Coolant System is performed considering various soil profiles and effects of concrete cracking. In this paper, the seismic responses of the APR1400 RCS is evaluated. The maximum RCS support and nozzle loads occur in the fixed base condition. As a soil profile goes to hard rock condition, the maximum seismic loads response tends to increase. Peak value of acceleration response spectra also occur in the fixed base condition. However, peaks are found in other cases in low frequency region. From this study, It is concluded that the seismic response from the fixed base condition governs the RCS seismic design.
APR1400 원자로냉각재계통 스너버의 비구속기능 상실의 영향 평가
황병천(Byung Chun Hwang),이한걸(Han Gul Lee),전장환(Jang Hwan Jheon),성기광(Ki Kwang Sung),김현민(Hyun Min Kim) 대한기계학회 2016 대한기계학회 춘추학술대회 Vol.2016 No.12
This study assesses the effects of a failure of snubber installed on two Steam Generators(SGs) and four Reactor Coolant Pumps(RCPs) in the APR1400 Reactor Coolant System(RCS) under normal operation(NOP) conditions. The analysis results show that the single snubber failure i.e., lockup, during the normal operation conditions has somewhat severe effects especially on the inlet nozzle of the SG and the outlet nozzle of the RCP. However, the resultant load increases on the RCS will be limited to a certain level since the failed snubber does not act as a restraint any more beyond the snubber load rate, and a stress evaluation reveals that the resultant stress intensities remain below the allowable. Additionally, the analysis results also show that the single snubber failure effects are confined to the component having the failed snubber. Accordingly, the single snubber failure in the RCS will not degrade the structural integrity of the RCS.