核电厂屏蔽主泵Canopy密封环钻孔疏流装置设计与研究  

Design and Research of Drilling and Draining Equipment for Canopy Seal Weld on CAP1400/AP1000 Canned Reactor Coolant Pump

作　　者：闫国华[1] 文忠[1] 李玮[1] 俞照辉[1] Yan Guohua;Wen Zhong;Li Wei;Yu Zhaohui(State Nuclear Power Plant Service Company,Shanghai,200233,China)

机构地区：[1]国核电站运行服务技术有限公司

出　　处：《核动力工程》2019年第4期145-148,共4页Nuclear Power Engineering

基　　金：国家重大科技专项“大型先进压水堆及高温气冷堆核电站”课题“CAP1400核电站运行和维护技术研究”(2015ZX06002005)

摘　　要：针对国和一号(CAP1400)、非能动先进压水堆(AP1000)核电机组屏蔽主泵拆装过程中残余放射性冷却剂如何导出的问题,研制了Canopy密封环钻孔疏流装置,并在试验台上进行了钻孔疏流试验。试验结果表明,Canopy密封环钻孔疏流装置密封效果达到了预期效果,未出现冷却剂外泄;刀具及切削参数选取合适,碎屑为细小碎片状,可随冷却剂一起导出;整套系统结构紧凑,工艺控制简单,能够实现远程控制的功能需求。The drilling equipment for the canopy seal weld was developed to drain the residual radioactive coolant from the steam generator during the disassembly of the canned reactor coolant pump in China Advanced Passive Power Plan t (CAP1400) and Advanced Passive Power Plant (AP1000). The results show that the expected sealing effect of the device is satisfied and there is no leakage of coolant during the whole process;the drill tool and machining parameters are optimized and the debris is small and fragmented, which can be drained with the coolant;the whole system is with compact structure and easy-control process, and can be remotely operated.

关 键 词：屏蔽主泵 残余放射性冷却剂 Canopy密封环 钻孔疏流 

分 类 号：TH17[机械工程—机械制造及自动化]