取消旁路后的冷却剂温度测量通道调试研究  

Research on Commissioning of Reactor Coolant Temperature Measurement Channel with Bypass Removed

作　　者：朱加良 何正熙[1] 杜茂 陈静[1] 余俊辉[1] 李小芬[1] 李红霞[1] 何鹏[1] 徐涛 ZHU Jialiang;HE Zhengxi;DU Mao;CHEN Jing;YU Junhui;LI Xiaofen;LI Hongxia;HE Peng;XU Tao(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu 610213,China;Fujian Fuqing Nuclear Power Co.,Ltd.,Fuqing 350318,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国家级重点实验室,四川成都610213 [2]福建福清核电有限公司,福建福清350318

出　　处：《自动化仪表》2019年第6期49-51,62,共4页Process Automation Instrumentation

摘　　要：传统M310核电厂采用旁路测量方式执行关键安全参数-反应堆冷却剂温度的测量。但该方式由于工艺回路复杂、主管道上接管数量多且维修难度大而不满足三代核电的要求,故在华龙一号核电厂中取消了旁路设计为主管道直接测温方式,由此带来反应堆冷却剂温度测量调试的变化。首先介绍了调试的过程并分析了导致调试变化的具体原因,然后针对该变化研究出具体的调试方案,最后论证新调试方案的可行性。论证结果表明:新的调试方案是可行的,且有利于电厂安全运行。Traditional M310 nuclear power plant adopted bypass measurement method to measure key safety parameter,the reactor coolant temperature,but this method featured complicated process loop,large amount of connection on the main pipeline and difficult maintenance that cannot satisfy the requirements of the 3 rd generation nuclear power which has been removed in HPR1000 nuclear power plant and replaced by primary pipeline direct temperature detection method,hence the commissioning of reactor coolant temperature measurement channel is changed.Firstly,the commissioning process is introduced,and the specific causes of the commissioning changes are analyzed.Then,the specific commissioning scheme is studied for the change.Finally,the feasibility of the new commissioning scheme is verified.The results of the verification show that the new commissioning scheme is feasible and beneficial to the safe operation of the power plant.

关 键 词：核电厂 M310 华龙一号 冷却剂温度测量 测温旁路 主管道直接测温 

分 类 号：TH-3[机械工程]