CAP系列核电站堆内外核测系统国产化探讨  

Discussion of Localization of Nuclear Instrumentation System for CAP Series NPP

作　　者：舒毅 汤仲鸣 胡铸萱 SHU Yi;TANG Zhongming;HU Zhuxuan(State Nuclear Power Technology Corporation,Beijing 100029,China;State Nuclear Power Automation System Engineering Company,Shanghai 200241,China)

机构地区：[1]国家核电技术公司,北京100029 [2]国核自仪系统工程有限公司,上海200241

出　　处：《自动化仪表》2018年第11期17-20,26,共5页Process Automation Instrumentation

摘　　要：当前,国家已制定非能动大型先进压水堆(CAP)系列核电站批量化建设的国家战略。堆内外核测系统是核电站关键仪控系统。与以往二代加核电站相比,第三代CAP系列核电站(NPP)堆内外核测系统的探测技术和设计理念存在较大的不同。针对CAP系列核电站堆内外核测系统的设计特点,从系统设计架构、实现的安全功能和主要性能参数等方面进行分析研究。对三代核电站堆内外核测系统相比国内以往的二代加核电站堆内外核测系统的设计优化和设计改进等方面进行梳理总结,提出目前国际上对于堆内外核测系统的主要发展趋势。同时,从堆内外核测系统关键设备的设备国产化角度,提出设备国产化的研制重点及难点,为将来实现设备国产化、自主化指明方向。Currently,China has formulated the national strategy to massively build CAP series nuclear power plants.As the key instrumentation control system for nuclear power plant(NPP),the detecting technology and design philosophy of 3 rd generation CAP series NPP in-core and ex-core instrumentation system are different from that of 2 nd plus generation NPP.According to the design features of in-core and ex-core nuclear instrumentation system for CAP series NPP,the analysis and research are carried out from the aspects of system design architecture,realized safety functions and main performance parameters.These summarize the design optimization and improvement of in-core and ex-core nuclear instrumentation system for 3 rd generation NPP that different from of 2 nd plus generation NPP.The development direction and trend worldwide of in-core and ex-core nuclear instrumentation system are pointed out;and the development focus and difficulties of localization of the equipment are proposed,to realize the localization and autonomy of equipment in the future.

关 键 词：核电 堆内外核测系统 国产化 裂变室 自给能探测器 堆芯热电偶 事故后监测 三维堆芯功率分布 

分 类 号：TH-39[机械工程] TP301.6[自动化与计算机技术—计算机系统结构]