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Recent Advances in Joining of Zirconium and Zirconium Alloy for Nuclear Industry

  • Nan Jiang,
  • Hong Bian,
  • Xiaoguo Song,
  • Yuzhen Lei,
  • Yanyu Song,
  • Danyang Lin,
  • Xiukai Chen,
  • Weimin Long

摘要

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.

Graphical Abstract