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反应堆保护系统动态可靠性建模与分析 被引量:8

Dynamic Reliability Modeling and Analysis for Reactor Protection System
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摘要 反应堆保护系统(RPS)是核电站最重要的安全设备之一。对该系统的可靠性评估一直备受关注。事件树和故障树等传统可靠性分析方法只能对反应堆保护系统进行静态分析,难以反映定期试验(PST)等检测和维修活动对系统可靠性的影响。动态分析方法中,马尔科夫模型一般适用于指数分布的情况,而反应堆保护系统的失效和维修过程,并不都服从指数分布。此外,很多模型都假设反应堆保护系统的各通道经过定期试验后都修复如新,这与实际情况也有差异。基于Petri网,建立了反应堆保护系统的动态可靠性模型,考虑了定期试验只维修故障通道的情况,描述了系统在不同状态之间的动态转换关系,计算了反应堆保护系统的瞬时可靠性。通过与理论值对比,验证了Petri网能很好地适用于反应堆保护系统的可靠性评估;并在假设反应堆保护系统失效过程服从不同分布的条件下,进行了可靠性分析。 Reactor protection system(RPS)is one of the most important safety equipment in nuclear power plant.The reliability assessment for RPS attracted considerable attention.Traditional reliability analysis methods,such as event tree and fault tree analysis,can only perform static reliability analysis on the RPS.And it is difficult to reflect the influence of periodic surveillance test(PST)and maintenance on system reliability by static methods.In the dynamic analysis methodology,Markov chain theory is only applicable to the event following exponential distribution,whereas the failure and maintenance processes did not always follow exponential distribution in RPS.In addition,many models assume that the channels of the RPS are always as good as new after PST,which is different from the actual situation.A dynamic reliability model of the RPS is established based on Petri nets,where only the faulty channel equipment detected by PST is replaced.The dynamic transition processes among different states are determined,and the instantaneous reliability of the RPS is presented.By comparing with the theoretical solution,it is verified that Petri nets is well suited for the reliability assessment of RPS.Moreover,the reliability analysis for RPS is carried out with the proposed model under the assumption that the failure process of the RPS is subject to different distributions.
作者 曹枭虓 熊华胜 郭超 张皓景 李铎 黄晓津 CAO Xiaoxiao;XIONG Huasheng;GUO Chao;ZHANG Haojing;LI Duo;HUANG Xiaojin(Institute of Nuclear and New Energy Technology of Tsinghua University,Collaborative Innovation Center of Advanced Nuclear Energy Technology,Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education,Beijing 100084,China)
出处 《自动化仪表》 CAS 2019年第6期6-10,共5页 Process Automation Instrumentation
基金 国家自然科学基金资助项目(71801141) 国家科技重大专项基金资助项目(ZX06902、ZX06906)
关键词 反应堆保护系统 可靠性评估 可靠性建模 定期试验 PETRI网 Reactor protection system(RPS) Reliability assessment Reliability modeling Periodic surveillance test Petri nets
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