大型钠冷快堆1E级DCS的紧急停堆系统可靠性计算分析与评价
The Reliability Calculation Analysis and Evaluation of the Safety DCS Emergency Shutdown System of the Large-scale Sodium Cooled Fast Reactor
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摘要: 国产1E级分布式控制系统(DCS)首次应用于大型钠冷快堆,其可靠性对反应堆的安全至关重要。针对大型钠冷快堆,采用独立于设计方马尔可夫分析法的故障树分析方法,选择保护系统中紧急停堆系统的拒动概率进行审评复核计算,建立故障树可靠性计算分析模型进行计算,并与设计方提供的可靠性计算结果比较分析。结果表明,1E级DCS保护系统中紧急停堆系统的拒动概率计算结果与设计方计算结果相对偏差在8%以内,两种方法的计算结果符合技术规格书要求,表明设计方计算结果是可接受的,为大型钠冷快堆1E级DCS的核安全审评提供了技术支持。Abstract: The domestically-made safety distributed control system(DCS) was first applied to the large-scale sodium cooled fast reactor, and its reliability is very important to the safety of reactor. For large-scale sodium cooled fast reactors, a fault tree analysis method independent of the designer’s Markov analysis method is used to select the rejection probability of the emergency shutdown system in the protection system for review and review calculations, and establish a fault tree reliability calculation analysis model, example calculation and analysis,and comparison with the reliability calculation results provided by the designer. The results show that the relative deviation between the rejection probability calculation results of the emergency shutdown system in the safety-level DCS protection system and the designer’s calculation is within 8%. The calculation results of the two methods meet the requirements of the technical specifications, indicate that the designer’s calculation is effective and credible, it provides technical support for the nuclear safety review of the safety-level DCS of the large-scale sodium cooled fast reactor.