Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking

被引：17
|
作者：
Wu, Bin [1 ,2 ]
Ming, Hongliang [1 ,2 ]
Meng, Fanjiang [3 ]
Li, Yifeng [4 ]
He, Guangqing [5 ,6 ]
Wang, Jianqiu [1 ,2 ]
Han, En-Hou [2 ]
机构：
[1] Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China
[2] Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
[3] Shanghai Nucl Engn Res & Design Inst Ltd Co, Shanghai 200233, Peoples R China
[4] Shanghai Univ, Instrumental Anal & Res Ctr, Shanghai 200444, Peoples R China
[5] Fudan Univ, Dept Mat Sci, Shanghai 200433, Peoples R China
[6] Shanghai Elect Nucl Power Equipment Co Ltd, Shanghai 201306, Peoples R China
来源：
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY | 2022年 / 113卷
基金：
中国国家自然科学基金;
关键词：
Alloy; 690TT; Scratch; Surface; Stress corrosion; High temperature corrosion; Intergranular corrosion; PRESSURIZED-WATER REACTORS; QUANTITATIVE ASSESSMENT; STAINLESS-STEEL; SECONDARY-SIDE; BEHAVIOR; RESISTANCE; SUBMODES; STRAIN;
D O I：
10.1016/j.jmst.2021.11.009
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Alloy 690TT tube samples with different scratch depths were repaired by grinding treatments using abrasive papers of two different particle sizes. The microstructure and stress corrosion cracking (SCC) behavior were studied in detail. During grinding, the plastic accumulation zone vulnerable to SCC was removed. Meanwhile, some residual slip steps remained in the scratched area. Corrosion tests lasting 10 0 0, 20 0 0, 30 0 0, and 40 0 0 h show that the sensitivity and risk of SCC in the scratched area are decreased by grinding. Treatment using abrasive particles of a smaller size is more effective. Nevertheless, deep scratches remained hazardous even after the grinding. (c) 2022 Published by Elsevier Ltd on behalf of The editorial office of Journal of Materials Science & Technology.
引用
收藏
页码：229 / 245
页数：17
相关论文
共 50 条
  • [1] Effect of surface scratch depth on microstructure change and stress corrosion cracking behavior of alloy 690TT steam generator tube
    Wu, Bin
    Ming, Hongliang
    Zhang, Zhiming
    Meng, Fanjiang
    Li, Yifeng
    Wang, Jianqiu
    Han, En-Hou
    CORROSION SCIENCE, 2021, 192
  • [2] The single effect of microstructure, residual strain and geometric structure on the stress corrosion cracking behavior of scratched alloy 690TT
    Wu, Bin
    Ming, Hongliang
    Li, Rongbo
    Meng, Fanjiang
    Wang, Jianqiu
    Han, En-Hou
    CORROSION SCIENCE, 2024, 227
  • [3] Insights into stress corrosion cracking in scratched area of alloy 690TT steam generator tubes
    Wu, Bin
    Zhang, Yusheng
    Meng, Fanjiang
    Zhang, Zhiming
    Li, Yifeng
    Wang, Jianqiu
    Han, En-Hou
    Ming, Hongliang
    ACTA MATERIALIA, 2023, 255
  • [4] Stress corrosion behavior of scratched Alloy 690TT steam generator tube in chlorine-containing high-temperature pressurized water
    Wu, Bin
    Meng, Fanjiang
    Zhang, Zhiming
    Li, Rongbo
    Ming, Hongliang
    Wang, Jianqiu
    Han, En-Hou
    MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION, 2022, 73 (10): : 1563 - 1574
  • [5] MICROSTRUCTURE NEAR SCRATCH ON ALLOY 690TT AND STRESS CORROSION INDUCED BY SCRATCHING
    Meng Fanjiang
    Wang Jianqiu
    Han En-Hou
    Shoji, Testuo
    Ke Wei
    ACTA METALLURGICA SINICA, 2011, 47 (07) : 839 - 846
  • [6] Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect
    Wu, Bin
    Ming, Hongliang
    Zhang, Zhiming
    Meng, Fanjiang
    He, Guangqing
    Wang, Jianqiu
    Han, En-Hou
    JOURNAL OF NUCLEAR MATERIALS, 2022, 563
  • [7] Development of prediction model for stress corrosion cracking probability in scratched alloy 690TT heat transfer tubes
    Li, Rongbo
    Wu, Bin
    Meng, Fanjiang
    Wang, Haitao
    Hou, Dongcen
    Ming, Hongliang
    Wang, Jianqiu
    Han, En-Hou
    CORROSION COMMUNICATIONS, 2025, 19 : 1 - 13
  • [8] Stress corrosion cracking behavior and mechanism of scratched Alloy 690TT in lead-containing caustic solution
    Li, Z. H.
    You, L.
    Wang, L.
    Zhang, X. F.
    Su, Y.
    Lu, Y. H.
    Shoji, T.
    CORROSION SCIENCE, 2025, 245
  • [9] Effects of scratching on corrosion and stress corrosion cracking of Alloy 690TT at 58 °C and 330 °C
    Meng, Fanjiang
    Wang, Jianqiu
    Han, En-Hou
    Ke, Wei
    CORROSION SCIENCE, 2009, 51 (11) : 2761 - 2769
  • [10] The mechanism of stress corrosion cracking of Alloy 690TT in a caustic solution containing lead
    Hou Qiang
    Liu Zhiyong
    Li Chengtao
    Li Xiaogang
    CORROSION SCIENCE, 2017, 128 : 154 - 163
12345