摘要
某核电站是国内早期引进的二代压水堆核电站,其棒控棒位系统(RGL)运行逾28年后进行了整体数字化改造。压水堆核电站为维持反应堆稳定运行配置了反应堆控制系统,其中包含反应堆平均温度调节系统、反应堆功率调节系统。这两个系统均通过RGL执行对温度控制棒和功率控制棒的提插控制实现系统功能。通过研究RGL对机组的响应功能要求,针对性地策划及实施了RGL数字化改造后对机组的响应功能试验,以验证RGL响应功能满足机组反应堆的稳定运行的要求。该试验方案可为国内外压水堆核电站RGL改造后RGL功能鉴定试验的设计提供参考,同时可为在役机组后续数字化改造后涉及反应堆运行功能的再鉴定方案制定提供有益借鉴。
A nuclear power plant is a second-generation pressurized water reactor nuclear power plant introduced early in China.After more than 28 years of operation,the rod control rod position system(RGL)has undergone a whole digital transformation.In order to maintain the stable operation of the reactor in PWR nuclear power plant,the reactor control system is configured,including the reactor average temperature regulation system and the reactor power regulation system,and the two systems are implemented by the RGL to carry out the lift and plug control of the temperature control rod and the power control rod to realize the system functions.By studying the response function requirements of the RGL to the unit,the response function test of the unit after the digital transformation of the RGL is planned and implemented to verify that the response function of the RGL meets the requirements of the stable operation of the unit reactor.This test scheme can provide a reference for the design of RGL function appraisal test after RGL modification in pressurized water reactor nuclear power plants at home and abroad,and can also provide a useful reference for the formulation of reappraisal scheme involving reactor operation function after subsequent digital transformation of servile units.
作者
韦桥
杨文清
柳继坤
WEI Qiao;YANG Wenqing;LIU Jikun(China Nuclear Power Engineering Co.,Ltd.,Shenzhen 518124,China)
出处
《自动化仪表》
CAS
2021年第S01期158-163,167,共7页
Process Automation Instrumentation
关键词
二代
核电站
棒控棒位系统
反应堆
控制系统
响应
试验
Second-generation
Nuclear power plant
Rod control rod position system
Reactor
Control system
Response
Test
作者简介
韦桥(1986-),男,学士,工程师,主要从事核电站堆芯核测及棒控棒位系统调试方向的研究,E-mail:armstrong_mosfire@126.com。
