摘要
CFR600示范快堆蒸汽发生器是我国自主设计、制造的四代核电堆型,本文主要介绍了CFR600示范快堆的产品结构、新型焊接材料研制以及技术控制要求,并详细论述了管子-管板封口焊技术、钠进出口接管与耐热不锈钢异种钢对接技术、铬钼钢(F22)与F91材料异种金属对接技术、超大壁厚铬钼钢环缝对接技术等关键焊接技术,为后续第四代核电堆型蒸汽发生器设计、研制提供技术保障。
CFR600 demonstration fast breeder reactor steam generator is the fourth Nuclear reactor designed by China.In this paper,the structural characteristics,the welding materials and the requirements of CFR600 steam generator was described.Meanwhile,the key welding processes to be implemented,such as the tube-to-tube sheet weld,Joint technology of sodium inlet and outlet pipe and heat-resistant stainless steel dissimilar steel,technology of dissimilar metal docking between chromium molybdenum steel(F22)and F91 material,ring joint technology of extra-large wall thick chromium molybdenum steel,have been introduced in detail,which provides technical supports for the design and development of the fourth generation nuclear power reactor steam generator.
作者
但军
李恩
蒋宇晨
邓道勇
戴光明
DAN Jun;LI En;JIANG Yuchen;DENG Daoyong;DAI Guangming(Dongfang(Guangzhou)Heavy Machinery Co.,Ltd.,511455,Guangzhou,China)
出处
《东方电气评论》
2023年第2期27-30,共4页
Dongfang Electric Review
关键词
快堆
核电技术
蒸汽发生器
焊接技术
fast breeder reactor
nuclear power technology
steam generator
welding technology