姚伟，杨浩，黄四和（福建福清核电有限公司，福建 福清 350318）

摘要：本文通过深入分析某核电厂反应堆保护系统停堆断路器异常动作原因，研究核安全级控制系统与非核安全级控制系统间通讯及扫描周期的差异性和反应堆保护系统仪表质量位设置的特殊性，明确保护 系统仪表质量位的阈值设计应该结合安全功能需求、工况和仪表特性进行综合考虑的原则，同时给出修改主蒸汽流量计超量程下限质量位阈值和调整机组下行时蒸汽发生器液位控制值的优化措施，增加了技术上和操作上的防护屏障，可以有效避免此类问题再次发生。该研究对核电厂机组安全稳定运行具有实际应用价值，并对后续机组及同行电厂保护系统动作机理研究具有借鉴意义。

关键词：核电厂；停堆断路器；保护系统；扫描周期；质量位

Abstract: The function of reactor protection system is to protect the  integrity of the three nuclear safety barriers，which is an important  system guarantee the safe operation of the reactor. Through indepth analysis of a nuclear power plant reactor protection system  trip breaker unexpected action, the differences of scan cycle in the  nuclear safety and non-safety control system and the particularity  of the quality bit are studied. It is clear that the design requirement  of quality bit threshold should be combined with the safety function  requirements, conditions, and instrument properties. At the same time,  the optimization measures of modifying the mass level threshold of the  main steam flowmeter over the lower limit of the range and adjusting  the control value of the steam generator liquid level when the unit goes  down are given. The technical and operational protection barriers are  added, which can effectively avoid the recurrence of such problems.  This research is valuable in application of safe and stable operation  of nuclear power plant, and provides some references for reactor  protection system action mechanism research of peer power plant. 

Key Words: Nuclear power plant; Reactor trip breaker; Protection  system; Scan cycle; Quality bit

在线预览：核反应堆保护系统停堆断路器异常动作分析研究.pd

摘自《自动化博览》2021年6月刊