金属加工（热加工）Issue(8)：17-25,32,10.
锆合金表面激光熔覆制备Ti-Cr涂层耐磨性能及腐蚀行为研究
Wear resistance and corrosion behavior of Ti-Cr coatings fabricated via laser cladding on zirconium alloy
摘要
Abstract
Zirconium(Zr)and its alloys are the preferred materials for nuclear fuel cladding due to their low neutron absorption cross-section,among other advantages.However,the harsh service environment inside nuclear reactors,characterized by high temperature,high pressure,intense radiation,and wear,significantly shortens the lifespan of zirconium alloy components.Chromium(Cr),known for its excellent wear and corrosion resistance,is often chosen as a surface coating material for Zr allovs.Nevertheless,pure Cr coatings are brittle and prone to cracking and other defects.Titanium(Ti),with its good plasticity,corrosion resistance,and strength,is introduced into Cr coatings to potentially address the cracking issues of pure Cr coatings.In this study,a Ti-Cr(mass percentage is 8∶2)coating was prepared on the surface of Zr-4 alloy using laser cladding technology to enhance the wear and corrosion resistance of the zirconium alloy surface.The prepared coating was dense,defect-free,and compositionally uniform,forming a strong metallurgical bond with the Zr-4 substrate through mutual dissolution.Compared to the Zr-4 substrate,the Ti-Cr coating exhibited a hardness of 415.4HV,which is 2.2 times that of the substrate,and a 35.3％reduction in abrasion wear rate,demonstrating excellent wear resistance.The electrochemical test results revealed that the Ti-Cr coating had a higher self-corrosion potential and lower self-corrosion current density than the Zr-4 substrate,indicating superior corrosion resistance.This research provides important insights for developing high-performance Zr-4 alloy coatings suitable for service in demanding environments.关键词
激光熔覆/Zr合金/Ti-Cr涂层/耐磨性/耐蚀性Key words
laser cladding/Zr alloy/Ti-Cr coating/wear resistance/corrosion resistance引用本文复制引用
罗华,龙绍军,任岩,连利仙,刘颖..锆合金表面激光熔覆制备Ti-Cr涂层耐磨性能及腐蚀行为研究[J].金属加工（热加工）,2025,(8):17-25,32,10.基金项目
四川省工程技术研究中心资助项目(2023GFW0462) （2023GFW0462）
中国核动力研究设计院联合创新基金项目(HG2023164). （HG2023164）
