Corrosion resistance of 316 stainless steel in a simulated pressurized water reactor improved by laser cladding with chromium

被引:38
作者
Gu, Yufen [1 ]
Xu, Youwei [1 ]
Shi, Yu [1 ]
Feng, Changgen [2 ]
Volodymyr, Korzhyk [2 ]
机构
[1] Lanzhou Univ Technol, State Key Lab Adv Proc & Recycling Nonferrous Met, Lanzhou 730050, Peoples R China
[2] Zhejiang EO Paton Welding Technol Inst, Hangzhou 311200, Peoples R China
基金
中国国家自然科学基金;
关键词
Laser cladding; Powder bed fusion; Oxidation behavior; Stress corrosion; Nuclear power plant; CRACK-GROWTH-RATE; MATERIALS CHALLENGES; BEHAVIOR; COATINGS; ALLOYS; FATIGUE; INITIATION; OXYGEN;
D O I
10.1016/j.surfcoat.2022.128534
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
Cr coatings were applied to the surface of 316 austenitic stainless steel (SS) by laser cladding. A comparison of the morphology, element distribution, electrochemical behavior, and oxidation behavior of the Cr coatings revealed that the Cr surface cladding significantly improved the corrosion resistance of 316 SS in a simulated primary circuit environment of a nuclear power plant. The Cr coatings performed the best when a laser power of 220 W was used. Analysis showed that the volume fraction of chromium oxides in the oxide film increased significantly in the samples with Cr coatings compared with the matrix sample. This inhibited the outward diffusion of metal elements from the 316 SS substrate, thereby improving the corrosion resistance of 316 SS.
引用
收藏
页数:9
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