在役核电站反应堆压力容器主螺栓卡涩处理和螺孔修复技术研究

Technology Study and Equipment Development of the Main Bolt Jamming Treatment and Screw Hole Reaming Repair for the Reactor Pressure Vessel in NPP

本文以国内新建压水堆核电站实际发生的反应堆压力容器主螺栓卡涩取出修复技术作为研究基础,旨在开发更高效率并且适用于已经投运核电站发生类似问题的技术工艺方法和成套设备。本文分析了已经投运电站的辐射环境影响和安装空间差异,梳理关键技术和制定技术路线;重点从工艺方法和设备功能集成两个方向进行研究;而后根据设备设计接口和工艺过程要求确定主要设计参数,开发设备,并描述工作过程;最后对核心设备进行现场环境模拟试验验证。

In this paper,based on the technical problems of main bolt jamming removal and reaming repair of reactor pressure vessel in newly built PWR nuclear power plant in China are taken as the research background,more efficient and suitable technical process and complete equipment for nuclear power plant are developed.This paper analyzes the radiation environmental impact and installation space differences of operating power plants,combs the key technologies and determines the technical route,and further optimizes and analyzes the process method,equipment and function integration.Then the main design parameters are determined according to the equipment design interface and process requirements,and then the equipment is developed and the working process is described.Finally,the core equipment is tested and verified by simulating the field environment and technical problems.