核电站一回路主承压设备的工作条件及其焊接的质量控制  

Working conditions and welding quality control of pressure retaining equipments in reactor coolant system of nuclear power plant

作　　者：韩佳泉 常凤华[2] 

机构地区：[1]黑龙江省电力科学研究院,哈尔滨市150030 [2]哈尔滨焊接技术培训中心,150046

出　　处：《焊接》2011年第1期37-41,71,共5页Welding & Joining

摘　　要：介绍了核电站一回路主承压设备的工作条件、设计理念和工况对用于制造一回路主承压设备的材料的性能要求,如常温和高温力学性能、耐蚀性能、吸收界面和感生放射性、辐射条件下的性能稳定性和力学加工性能,并从事前控制、事中控制和事后控制三个方面阐述了一回路主承压设备在制造过程中的焊接质量保证与控制措施。The working conditions of pressure retaining components in reactor coolant system of nuclear power plant were introduced,the performance requirements of materials used in the reactor coolant system components such as mechanical properties at room and elevated temperature, corrosion resistance,absorption interface and induced radioactivity,performance stability under the condition of constant radiation and machinability were discussed.The measures to control and assure the welding quality in manufacturing the pressure retaining components of reactor coolant system were discussed from the control before,in and after manufacturing.

关 键 词：核电站 一回路主承压设备 焊接 质量控制 

分 类 号：TG441.7[金属学及工艺—焊接]