某核电厂燃料包壳破损监测技术研究  

Study on the Monitoring Technology of Fuel Cladding Damage in a Nuclear Power Plant

作　　者：陈小强 魏学虎 熊军 刘杰 CHEN Xiaoqiang;WEI Xuehu;XIONG Jun;LIU Jie(China Nuclear Power Engineering Co.,Ltd.,Shenzhen of Guangdong Prov.518100,China)

机构地区：[1]中广核工程有限公司,广东深圳518100

出　　处：《核科学与工程》2024年第5期1186-1191,共6页Nuclear Science and Engineering

摘　　要：燃料包壳破损监测是评价第一道屏障完整性及保障核电厂安全运行的重要手段,核电厂现有监测设备体积庞大、监测方法存在误报警等缺点。本文就某核电厂燃料包壳破损监测方法和报警控制逻辑设计缺陷而导致的非燃料包壳破损的真实报警问题,提出了γ耦合的燃料包壳破损监测方法,优化报警控制逻辑并实施报警信号延迟措施,从根本上消除某核电厂燃料包壳破损监测的误报警问题。Fuel cladding damage monitoring is an important means to evaluate the integrity of the first barrier and ensure the safety operation of power plants.The monitoring equipment is bulky and the monitoring methods have some shortcomings in nuclear power plants,such as false alarms.Aiming at the problem for the real alarm of non-fuel cladding damage caused by the design defects of the fuel cladding damage monitoring method and the alarm control logic in a nuclear power plant,a gamma coupled fuel cladding damage monitoring method is proposed,and the alarm control logic is optimized and the alarm signal delay measures are implemented to fundamentally eliminate the false alarm problem of fuel cladding damage monitoring in a nuclear power plant.

关 键 词：包壳破损监测 活化腐蚀产物 一回路冷却剂 报警阈值 

分 类 号：TL812[核科学技术—核技术及应用]