华龙一号海外首堆反应堆控制系统优化设计  

Optimization Design for Reactor Control System of the First Overseas HPR1000 Reactor

作　　者：张英[1] Zhang Ying(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点试验室,成都610213

出　　处：《核动力工程》2022年第5期245-249,共5页Nuclear Power Engineering

摘　　要：反应堆控制系统是核电厂重要仪控系统之一,对保障核电厂的正常运行起着重要作用。为确保控制系统在核电厂运行过程中的良好控制品质和减少现场调试时间,有必要在设计阶段通过仿真研究对控制系统参数进行优化设计。分析了三代核电华龙一号(HPR 1000)海外首堆的反应堆控制系统功能,对各控制系统被控变量进行了说明;在此基础上,对控制系统参数优化流程进行说明;利用核电厂数字化仿真工具,通过系统建模仿真对控制系统参数进行敏感性分析,根据不同参数取值下的系统静态和动态响应特性得到较优的控制系统参数,经性能验证满足设计要求。所获得的反应堆控制系统参数已用于海外华龙一号首堆反应堆控制系统设计,并用于指导核电厂现场调试和核电厂运行。Reactor control system is an important instrument and control system and plays a significant role in the normal operation of the nuclear power plant(NPP).In order to guarantee the good control performance of the control system during the normal operation of NPP and to decrease the on-site commissioning time,it is necessary to optimize the control parameters through simulation study on the control system in the design phase.This paper analyzes the reactor control system functions of the first overseas third-generation HPR1000 reactor,and describes the controlled variables of each control system.On this basis,the optimization of control system parameters is described.Using the NPP digital simulation tool,the sensitivity analysis of the control system parameters is carried out through system modeling and simulation,and the optimal control system parameters are obtained according to the static and dynamic response characteristics of the system under different parameter values,and such parameters meet the design requirements through performance verification.The obtained reactor control system parameters have been used in the design of the reactor control system of first overseas HPR100 reactor,and used to guide the on-site commissioning and operation of NPP.

关 键 词：反应堆控制系统 控制系统参数 系统仿真 参数优化 

分 类 号：TL362[核科学技术—核技术及应用]