Nan Jiang, Hong Bian, Xiaoguo Song, Yuzhen Lei, Yanyu Song, Danyang Lin, Xiukai Chen, Weimin Long
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Abstract
Due to its moderate mechanical properties, low neutron absorption, excellent processability, superior irradiation, and corrosion resistance, as well as good compatibility with nuclear fuel, zirconium (Zr) and its alloys have been extensively employed as fuel cladding tubes and structural materials in the nuclear industry. This review examines research progress on the joining of Zr alloy with dissimilar materials over the past 20 years, encompassing friction welding, fusion welding, diffusion bonding, brazing and resistance welding. It also compares and analyzes the impact of these welding methods and processes on the mechanical properties and microstructure of Zr alloy joints. Finally, the paper addresses the future direction of Zr alloy joining. Aimed at discussing and analyzing recent progress in the joining of Zr and dissimilar materials, this review lays the groundwork for subsequent research related to Zr joining in the nuclear industry.
期刊介绍：
Metals and Materials International publishes original papers and occasional critical reviews on all aspects of research and technology in materials engineering: physical metallurgy, materials science, and processing of metals and other materials. Emphasis is placed on those aspects of the science of materials that are concerned with the relationships among the processing, structure and properties (mechanical, chemical, electrical, electrochemical, magnetic and optical) of materials. Aspects of processing include the melting, casting, and fabrication with the thermodynamics, kinetics and modeling.
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