核电厂停堆断路器停堆控制接口设计  

Design of the Control Interface of Reactor Trip Breaker in Nuclear Power Plant

作　　者：周叶翔 田亚杰 任立永 刘光明 江辉 

机构地区：[1]深圳中广核工程设计有限公司,广东深圳518172

出　　处：《自动化仪表》2015年第11期93-96,共4页Process Automation Instrumentation

基　　金：国家科技重大专项基金资助项目(编号:K-B2012.058)

摘　　要：压水堆核电厂普遍采用停堆断路器作为紧急停堆系统的执行机构。通过对当前多种停堆控制接口方案的研究分析,指出当前的设计方案在某些工作瞬态下存在两个隐患:停堆线圈的负载与控制平台的带载能力失配;停堆断路器欠压线圈控制回路间存在电路耦合。针对这两个问题,根据相关标准法规要求,采用二极管电路解耦方法及中间继电器解耦方法,分别提出一种改进方案,为后续核电厂停堆控制接口的设计及改造提供参考。In PWR nuclear power plants, the reactor trip breakers are commonly used as the actuators of emergency reactor trip system. Through researching and analyzing various existing trip control interface schemes, two hidden dangers in current designing schemes are pointed out, i. e. , the load of the trip coil don' t match with the load capacity of the control platform;and the circuit coupling is existing among control loops of the under voltage coils of trip breakers. To against these two problems, in accordance with related standards and regulations, improving schemes are proposed respectively by using dioxide circuit decoupling method and intermediate relay decoupling method, these provide reference for designing trip control interface of subsequent nuclear power plants.

关 键 词：压水堆核电厂 保护系统 停堆断路器 线圈 电路耦合 标准 

分 类 号：TH-39[机械工程] TP273[自动化与计算机技术—检测技术与自动化装置]