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基于FPGA的核安全级仪控系统设计与验证 被引量:3

Design and Verification on Nuclear Safety Class Digital Instrument Control System Based on FPGA
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摘要 为解决基于微处理器技术的核电厂安全级数字化仪控系统(DCS)中软件共因故障(CCF)的问题,通过多样性手段避免当未能紧急停堆的预计瞬态(ATWS)发生或反应堆保护系统(RPS)因CCF导致丧失安全功能的风险,本文设计了一种基于现场可编程逻辑门阵列(FPGA)技术的核安全级DCS系统平台,并以核电厂中RPS为实例测试验证平台的功能性能。结果表明:基于FPGA的核安全级DCS系统平台在可用性、适用性和可靠性等方面都满足核电厂安全级数字化仪控系统的要求。 The common cause failure(CCF) due to the software design of the digital safety class instrument and control(I&C) system based on micro-processor technology for NPP is resolved by the diversity measures implemented based on FPGA, which could prevent the failure of the reactor protection system(RPS) when the Anticipated Transients Without Scram(ATWS) occurs. This paper presents the design of overall system, platform hardware and platform logic implemented with FPGA technology. The design is further validated for its capability and performance by RPS system of a nuclear power plant, demonstrating that the DCS system in this study is consistent to the requirement of digital safety I&C for NPP on feasibility, applicability and reliability.
作者 马晓宇 黄晓津 王冬 Ma Xiaoyu;Huang Xiaojin;Wang Dong(Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing,100045,China;China National Nuclear Corporation(CNNC),Beijing,100840,China;China Nuclear Control System Engineering Co.,Ltd.,Beijing,102401,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2021年第2期115-120,共6页 Nuclear Power Engineering
关键词 核安全级 数字化仪控系统(DCS) 软件共因故障(CCF) 现场可编程逻辑门阵列(FPGA) 反应堆保护系统(RPS) Nuclear safety class Digital instrument and control system(DCS) Common cause failure(CCF) FPGA Reactor protection system(RPS)
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