摘要
ODS钢具有优异的高温力学性能、抗辐照性能和抗热蠕变性能等,是最有潜力的下一代核反应堆包壳候选材料之一。ODS钢的焊接技术主要包括熔焊、钎焊、压力焊等,根据核燃料元件包壳结构,选择电子束焊接、旋转摩擦焊及脉冲电流辅助扩散焊三种焊接方法进行对比研究,并对ODS钢焊接接头微观形貌演化进行分析,揭示了最优焊接方法及界面形貌演化规律。结果表明,电子束焊接及旋转摩擦焊接工艺下,焊接接头的晶界处均有Y_(2)O_(3)析出,而采用脉冲电流辅助扩散焊无氧化物析出和团聚,对于Fe-Cr系ODS钢有突出优势。因此,脉冲电流辅助扩散焊在抑制ODS钢中纳米氧化物的析出、团聚和减少接头变形等方面具有显著优势,是一种适合ODS钢焊接的高质量焊接方法。
ODS steel has excellent high-temperature mechanical properties,radiation resistance,and thermal creep resis‐tance,and is one of the most potential candidate materials for the next generation nuclear reactor fuel element cladding.The welding technology of ODS steel mainly includes fusion welding,brazing,pressure welding,etc.According to the cladding structure of nuclear fuel elements,three welding methods,namely electron beam welding,rotary friction welding,and pulse current assisted diffusion welding,are selected for comparative study,and their microscopic morphology evolution is ana‐lyzed to reveal the optimal welding method and the evolution law of interface morphology.The results show that Y_(2)O_(3) pre‐cipitates at the grain boundaries of the welded joints under electron beam welding and rotary friction welding processes,and pulse current assisted diffusion welding has no oxide precipitation and agglomeration.Pulse current assisted diffusion weld‐ing has prominent advantages for Fe-Cr ODS steels.
作者
杨灿湘
魏连峰
郑勇
王宇
董宇
王军健
李华鑫
杨建国
张鸿羽
侯霭麟
YANG Canxiang;WEI Lianfeng;ZHENG Yong;WANG Yu;DONG Yu;WANG Junjian;LI Huaxing;YANG Jianguo;ZHANG Hongyu;HOU Ailin(Nuclear Power Institute of China,The Key Nuclear Fuel and Nuclear Materials Laboratory of China,Chengdu 610041,China;Zhejiang University of Technology,School of Mechanical Engineering Physics,Hangzhou 310023,China)
出处
《电焊机》
2024年第5期39-45,共7页
Electric Welding Machine
基金
中核集团青年英才科研项目(JT233)。
关键词
ODS钢
核燃料元件焊接
电子束焊接
旋转摩擦焊接
脉冲电流辅助扩散焊接
oxide dispersion strengthened steel
nuclear fuel element welding
electron beam welding
rotary friction welding
pulsed current assisted diffusion welding
