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姚偉，楊浩，黃四和（福建福清核電有限公司，福建 福清 350318）

摘要：本文通過深入分析某核電廠反應堆保護系統停堆斷路器異常動作原因，研究核安全級控制系統與非核安全級控制系統間通訊及掃描周期的差異性和反應堆保護系統儀表質量位設置的特殊性，明確保護 系統儀表質量位的閾值設計應該結合安全功能需求、工況和儀表特性進行綜合考慮的原則，同時給出修改主蒸汽流量計超量程下限質量位閾值和調整機組下行時蒸汽發生器液位控制值的優化措施，增加了技術上和操作上的防護屏障，可以有效避免此類問題再次發生。該研究對核電廠機組安全穩定運行具有實際應用價值，并對后續機組及同行電廠保護系統動作機理研究具有借鑒意義。

關鍵詞：核電廠；停堆斷路器；保護系統；掃描周期；質量位

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

在線預覽：核反應堆保護系統停堆斷路器異常動作分析研究.pd

摘自《自動化博覽》2021年6月刊