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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(yīng)堆保護(hù)系統(tǒng)停堆斷路器異常動(dòng)作原因，研究核安全級(jí)控制系統(tǒng)與非核安全級(jí)控制系統(tǒng)間通訊及掃描周期的差異性和反應(yīng)堆保護(hù)系統(tǒng)儀表質(zhì)量位設(shè)置的特殊性，明確保護(hù) 系統(tǒng)儀表質(zhì)量位的閾值設(shè)計(jì)應(yīng)該結(jié)合安全功能需求、工況和儀表特性進(jìn)行綜合考慮的原則，同時(shí)給出修改主蒸汽流量計(jì)超量程下限質(zhì)量位閾值和調(diào)整機(jī)組下行時(shí)蒸汽發(fā)生器液位控制值的優(yōu)化措施，增加了技術(shù)上和操作上的防護(hù)屏障，可以有效避免此類問題再次發(fā)生。該研究對(duì)核電廠機(jī)組安全穩(wěn)定運(yùn)行具有實(shí)際應(yīng)用價(jià)值，并對(duì)后續(xù)機(jī)組及同行電廠保護(hù)系統(tǒng)動(dòng)作機(jī)理研究具有借鑒意義。

關(guān)鍵詞：核電廠；停堆斷路器；保護(hù)系統(tǒng)；掃描周期；質(zhì)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(yù)覽：核反應(yīng)堆保護(hù)系統(tǒng)停堆斷路器異常動(dòng)作分析研究.pd

摘自《自動(dòng)化博覽》2021年6月刊