The structure dependence of oxidation behavior of high-angle grain boundaries of alloy 600 in simulated pressurized water reactor primary water

被引:5
|
作者
Feng, Xingyu [1 ]
Wang, Qi [1 ]
Xie, Jiayu [1 ]
Kuang, Wenjun [1 ]
机构
[1] Xi An Jiao Tong Univ, Ctr Adv Mat Performance Nanoscale CAMP Nano, State Key Lab Mech Behav Mat, Xian 710049, Peoples R China
基金
中国国家自然科学基金;
关键词
Alloy; 600; STEM; Grain boundary diffusion; Grain boundary migration; Intergranular oxidation; STRESS-CORROSION CRACKING; PREFERENTIAL INTERGRANULAR OXIDATION; QUANTITATIVE ASSESSMENT; SECONDARY-SIDE; INTERNAL OXIDATION; STAINLESS-STEEL; MIGRATION; NICKEL; STEAM; NI;
D O I
10.1016/j.corsci.2023.111162
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The intergranular degradation of seven different types of high-angle grain boundaries (HAGBs) were investigated on Alloy 600 after exposure to simulated pressurized water reactor primary water. All boundaries are susceptible to preferential intergranular oxidation (PIO) except for ideal coherent twin boundary. Diffusion induced grain boundary migration (DIGM) normally occurs and its depth is positively correlated with the PIO extent. Interestingly, the PIO susceptibility is independent on the grain boundary misorientation angle or & sigma; value, but related to the grain boundary atom packing density (GBAPD). Grain boundaries with higher GBAPD values show higher PIO resistance as the element diffusion is slower.
引用
收藏
页数:13
相关论文
共 50 条
  • [41] Effects of precipitation on the stress corrosion crack initiation of alloy 718 in simulated pressurized water reactor primary environment
    Ning, Zehao
    Zhang, Haoran
    Zhang, Shihao
    Hao, Xianchao
    Han, En-Hou
    Kuang, Wenjun
    [J]. ACTA MATERIALIA, 2024, 276
  • [42] Investigation of Fatigue Crack Propagation Behavior on the Surface of Machining Notches of Alloy 690TT in Simulated Pressurized Water Reactor Water
    Fu, Zhenghong
    Gou, Guoqing
    Xiao, Jun
    Qiu, Shaoyu
    Liu, Jinyun
    Zha, Wusheng
    Wang, Wanjing
    Yang, Yuping
    [J]. CORROSION, 2017, 73 (10) : 1258 - 1267
  • [43] Linking Grain Boundary Microstructure to Stress Corrosion Cracking of Cold-Rolled Alloy 690 in Pressurized Water Reactor Primary Water
    Bruemmer, S. M.
    Olszta, M. J.
    Toloczko, M. B.
    Thomas, L. E.
    [J]. CORROSION, 2013, 69 (10)
  • [44] The effect of elastic and plastic strain on surface and intergranular oxidation of alloy 600 in simulated PWR primary water
    Chen, H.
    Couvant, T.
    Seyeux, A.
    Duhamel, C.
    Marcus, P.
    [J]. CORROSION SCIENCE, 2023, 221
  • [45] Fatigue Life of the Strain Hardened Austenitic Stainless Steel in Simulated Pressurized Water Reactor Primary Water
    Huin, Nicolas
    Tsutsumi, Kazuya
    Couvant, Thierry
    Henaff, Gilbert
    Mendez, Jose
    [J]. JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2014, 136 (03):
  • [46] Effect of Thermal Treatment on Stress Corrosion Cracking Susceptibility in Alloy 600 and Type 316 Stainless Steel Under Simulated Pressurized Water Reactor Primary Conditions
    Kanzaki, Manabu
    Masaki, Yasuhiro
    Kudo, Takeo
    [J]. CORROSION, 2015, 71 (01) : 57 - 64
  • [47] The structure dependence of grain boundary passivation of Alloy 690 in high temperature water
    Feng, Xingyu
    Zhang, Shihao
    Liu, Pengshuai
    Kuang, Wenjun
    [J]. ACTA MATERIALIA, 2023, 261
  • [48] High-Temperature Electrochemical Corrosion Behavior of Fe-Cr-Ni Alloys in Simulated Pressurized Water Reactor Water
    Zhang, Le-fu
    Wang, Jia-mei
    [J]. CORROSION, 2018, 74 (04) : 415 - 423
  • [49] Early corrosion behaviour of irradiated FeCrAl alloy in a simulated pressurized water reactor environment
    Wu, Weisong
    Ran, Guang
    Li, Yipeng
    Cong, Shuo
    Ye, Chao
    Zhang, Ruiqian
    Sun, Yongduo
    [J]. CORROSION SCIENCE, 2020, 174
  • [50] Effect of Water Jet Cavitation Peening on Short-Period Oxidation Behavior of Alloy 600 in PWR Primary Water
    Ming, Tingyun
    Peng, Qunjia
    Han, Yaolei
    Zhang, Tao
    [J]. METALS, 2023, 13 (02)