Instrumentation and control (I&C) system is central nervous system of nuclear power plant (NPP), so its reliability is very important for the safety of NPP. Now Digital I&C system (DICS) is widely used in NPP, its reliability should be analyzed more carefully due to the more complex interaction among its components than analog I&C system. The interaction among DICS can be divided into type I and type II. The former is the interaction among sensor failure, controller failure and actuator failure, the latter is the interaction among hardware\software components of DICS. Limited by static Boolean logic, traditional fault tree is hard to model the dynamic interaction among DICS, so dynamic modelling method is required. In this paper, Dynamic flowgraph methodology (DFM) is used for reliability analysis of a subsystem of NPP DICS, namely APC (Automatic Power Control System). The proposed dynamic flowgraph modelled type I and type II interaction among APC and reliability of APC is assessed via inductive and deductive analysis. In the inductive analysis, three basic events (user defined combination of states) are considered, which includes sensor failure, SRB failure and master\checker processor failure, and the sequence of events caused by these basic events are tracked. In the deductive analysis, top event (combinations of possible system parameters and/or component states) is defined as actual control rod position is lower than demanded, and four combinations of basic events are tracked according to occurrence probability of their corresponding event.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5004-6
PROCEEDINGS PAPER
Reliability Analysis of the Automatic Control System of Reactor Power in Nuclear Power Plant Based on DFM
Wang Hao,
Wang Hao
North China Electric Power University, Beijing, China
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Tian Cong,
Tian Cong
North China Electric Power University, Beijing, China
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Zhou Shiliang,
Zhou Shiliang
North China Electric Power University, Beijing, China
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Liu Yu Yuan,
Liu Yu Yuan
North China Electric Power University, Beijing, China
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Shahroze Ahmad
Shahroze Ahmad
North China Electric Power University, Beijing, China
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Wang Hao
North China Electric Power University, Beijing, China
Tian Cong
North China Electric Power University, Beijing, China
Zhou Shiliang
North China Electric Power University, Beijing, China
Liu Yu Yuan
North China Electric Power University, Beijing, China
Shahroze Ahmad
North China Electric Power University, Beijing, China
Paper No:
ICONE24-60833, V004T14A018; 9 pages
Published Online:
October 25, 2016
Citation
Hao, W, Cong, T, Shiliang, Z, Yu Yuan, L, & Ahmad, S. "Reliability Analysis of the Automatic Control System of Reactor Power in Nuclear Power Plant Based on DFM." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management. Charlotte, North Carolina, USA. June 26–30, 2016. V004T14A018. ASME. https://doi.org/10.1115/ICONE24-60833
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