摘要
大亚湾核电厂辅助给水系统的疏水管道属RCC-M2级设备,因该设备在高温和高压差下导致疏水器和隔离阀处经常发生闪蒸和冲刷,致使其密封面损坏而发生疏水故障。为避免对系统产生影响,核电厂借鉴同类型机组的改进经验,通过增加备用隔离阀解决该问题。改进的管道依据RCC-M进行力学分析。
Drain pipeline of auxiliary feed water system in Daya Bay nuclear power plant is classified as RCC-M2 component. In this component,high temperature and high pressure difference lead to erosion and sealing surface damage for valves steam trap. In order to avoid influence to system,Daya Bay nuclear power plant uses modification experiences of other units for reference,and solves this problem by adding standby isolation valve. The piping improvement is calculated and analyzed according to RCC-M.
出处
《核安全》
2013年第4期6-9,共4页
Nuclear Safety
基金
国家科技支撑计划项目
百万千瓦级压水堆核电站控制棒驱动系统研究开发
课题编号:2011BAA06B01
