본 연구에서는 다중오동작을 포함하고 있는 화재안전정지분석 교육자료를 개발하기 위하여 가상원전에서의 화재안전정지분석을 결정론적 화재분석코드를 사용하여 수행하였다. 교육용 가상원전은 원자로건물과 보조건물로 이루어졌고, 총 22개의 방화지역으로 구성되었다. 교육용 가상원전의 각 방화지역에는 밸브, 펌프, 비상디젤발전기, 스위치기어, 모터제어반, 로직컨트롤러 등의 기기가 배치되었다. 교육용 가상원전 기기들은 두 개의 케이블로 연결되었으며, 각 케이블은 케이블 트레이를 따라서 방화지역을 지나간다고 가정했다. 방화지역분석을 위해 교육용 가상원전에 대한 기기 및 케이블 정보를 데이터베이스화하였고, 다중오동작 시나리오, 기기로직 및 케이블로직을 가정하여 방화지역분석을 수행하였다. 방화지역 분석결과 문제가 되는 케이블과 케이블 트레이에 대해서 3시간 내화성능으로 케이블을 래핑하는 완화조치를 적용하였다.
본 연구에서는 다중오동작을 포함하고 있는 화재안전정지분석 교육자료를 개발하기 위하여 가상원전에서의 화재안전정지분석을 결정론적 화재분석코드를 사용하여 수행하였다. 교육용 가상원전은 원자로건물과 보조건물로 이루어졌고, 총 22개의 방화지역으로 구성되었다. 교육용 가상원전의 각 방화지역에는 밸브, 펌프, 비상디젤발전기, 스위치기어, 모터제어반, 로직컨트롤러 등의 기기가 배치되었다. 교육용 가상원전 기기들은 두 개의 케이블로 연결되었으며, 각 케이블은 케이블 트레이를 따라서 방화지역을 지나간다고 가정했다. 방화지역분석을 위해 교육용 가상원전에 대한 기기 및 케이블 정보를 데이터베이스화하였고, 다중오동작 시나리오, 기기로직 및 케이블로직을 가정하여 방화지역분석을 수행하였다. 방화지역 분석결과 문제가 되는 케이블과 케이블 트레이에 대해서 3시간 내화성능으로 케이블을 래핑하는 완화조치를 적용하였다.
In this study, a post-fire safe shutdown analysis (PFSSA) including multiple spurious operation (MSO) treatments for cables was conducted with an imaginary nuclear power plant for training using a deterministic fire analysis code. The imaginary nuclear power plant for the training consisted of a rea...
In this study, a post-fire safe shutdown analysis (PFSSA) including multiple spurious operation (MSO) treatments for cables was conducted with an imaginary nuclear power plant for training using a deterministic fire analysis code. The imaginary nuclear power plant for the training consisted of a reactor containment building and an auxiliary building, including a total of 22 fire areas. The equipment including valves, pumps, emergency diesel generators, switch gears, motor control centers, and logic controllers were located in each fire area of the imaginary plant. It was assumed that each equipment is connected with two cables and that each cable passes through the fire areas along the cable trays. A database containing the information on the equipment and cables for the imaginary plant was constructed for the fire area analysis. The fire area analysis was performed for several assumed MSO scenarios, equipment logics, and cable logics. A mitigation measure using a three hour rated wrap was applied to the failed cables and cable trays after the fire area analysis.
In this study, a post-fire safe shutdown analysis (PFSSA) including multiple spurious operation (MSO) treatments for cables was conducted with an imaginary nuclear power plant for training using a deterministic fire analysis code. The imaginary nuclear power plant for the training consisted of a reactor containment building and an auxiliary building, including a total of 22 fire areas. The equipment including valves, pumps, emergency diesel generators, switch gears, motor control centers, and logic controllers were located in each fire area of the imaginary plant. It was assumed that each equipment is connected with two cables and that each cable passes through the fire areas along the cable trays. A database containing the information on the equipment and cables for the imaginary plant was constructed for the fire area analysis. The fire area analysis was performed for several assumed MSO scenarios, equipment logics, and cable logics. A mitigation measure using a three hour rated wrap was applied to the failed cables and cable trays after the fire area analysis.
U.S. NRC, "EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities (NUREG/CR-6850)", United States Nuclear Regulatory Commission, Washington, DC (2005).
U.S. NRC, "Fire Protection for Operating Nuclear Power Plants (Regulatory Guide 1.189)", United States Nuclear Regulatory Commission, Washington, DC (2009).
NEI 00-01, "Guidance for Post Fire Safe Shutdown Circuit Analysis", Nuclear Energy Institute, Washington, DC (2009).
J. Lee, J. Kim, and K. Kim, "How to Use EDISON/SAFE Codes for MSO Analysis", Proceedings of 2016 Spring Annual Conference, Korean Institute of Fire Science & Engineering, pp. 51-52 (2016).
J. Lee and T. Kim, "A Study on Technology Trends of Post Fire Safe Shutdown Analysis Considering Multiple Spurious Operation", Proceedings of 2015 Fall Annual Conference, the Korea Society for Energy Engineering, p. 149 (2015).
J. Lee and J. Kim, "Development of a Virtual Nuclear Power Plant for EDISON/SAFE Code Training", Proceedings of 2017 Fall Annual Conference, the Korea Society for Energy Engineering, p. 139 (2017).
※ AI-Helper는 부적절한 답변을 할 수 있습니다.