数字化核电厂反应堆冷却剂温度测量通道校准试验研究  

Study on Reactor Coolant Temperature Channel Calibration Test in Digital Control Nuclear Power Plants

作　　者：霍雨佳[1] 李红霞[1] 李亮[2] 陈静[1] 李小芬[1] 朱加良 

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实验室,成都610041 [2]环境保护部核与辐射安全中心,北京100082

出　　处：《核动力工程》2015年第2期77-80,共4页Nuclear Power Engineering

摘　　要：介绍反应堆冷却剂温度测量通道校准(TP RCP63)试验的内容,分析数字化技术对核电厂TP RCP63试验的影响,着重论述与模拟技术核电厂相比存在的变化与问题,并提出采用数字化技术后核电厂TP RCP63试验中温差、平均温度加法器系数以及温度信号的校准设计方案。The paper introduces the content of the TP RCP63 test simply, and analyzes the effect on the test due to the abroad application of digital control systems. Furthermore, the paper emphasizes the study of the difference and corresponding problems in the test comparing with the nuclear power plants with the analogue technology. As to the problems, the corresponding design solution are provided for the temperature difference, the coefficient of average temperature summer and the temperature signals calibration in TP RCP63 test of the digital nuclear power plants.

关 键 词：反应堆冷却剂 温度测量通道 校准试验 

分 类 号：TL363[核科学技术—核技术及应用]