Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant:Microstructure and stress corrosion cracking
Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking作者机构:School of Materials Science and EngineeringUniversity of Science and Technology of ChinaShenyang 110016China Key Laboratory of Nuclear Materials and Safety AssessmentInstitute of Metal ResearchChinese Academy of SciencesShenyang 110016China Shanghai Nuclear Engineering Research and Design Institute Ltd.Co.Shanghai 200233China Instrumental Analysis and Research CenterShanghai UniversityShanghai 200444China Department of Materials ScienceFudan UniversityShanghai 200433China Shanghai Electric Nuclear Power Equipment Co.Ltd.Shanghai 201306China
出 版 物:《Journal of Materials Science & Technology》 (材料科学技术(英文版))
年 卷 期:2022年第113卷第18期
页 面:229-245页
核心收录:
学科分类:080503[工学-材料加工工程] 080802[工学-电力系统及其自动化] 0808[工学-电气工程] 08[工学] 0805[工学-材料科学与工程(可授工学、理学学位)] 0802[工学-机械工程] 080201[工学-机械制造及其自动化]
基 金:jointly supported by National Natural Science Foundation of China (No. 51771211) National Key R&D Program(2019YFB1900904) the open-ended fund of the CAS Key laboratory of Nuclear Materials and Safety Assessment (Institute of Metal Research, Chinese Academy of Sciences, China)(No.2021NMSAKF01)
主 题:Alloy 690TT Scratch Surface Stress corrosion High temperature corrosion Intergranular corrosion
摘 要:Alloy 690TT tube samples with different scratch depths were repaired by grinding treatments using abra-sive papers of two different particle *** microstructure and stress corrosion cracking(SCC)behavior were studied in *** grinding,the plastic accumulation zone vulnerable to SCC was ***,some residual slip steps remained in the scratched *** tests lasting 1000,2000,3000,and 4000 h show that the sensitivity and risk of SCC in the scratched area are decreased by *** using abrasive particles of a smaller size is more ***,deep scratches remained hazardous even after the grinding.