Characterization of internal and intergranular oxidation in Alloy 690 exposed to simulated PWR primary water and its implications with regard to stress corrosion cracking

被引:17
|
作者
Lim, Yun Soo [1 ]
Kim, Dong Jin [1 ]
Kim, Sung Woo [1 ]
Hwang, Seong Sik [1 ]
Kim, Hong Pyo [1 ]
机构
[1] Korea Atom Energy Res Inst, Safety Mat Technol Dev Div, 989-111 Daedeok Daero, Daejeon 34057, South Korea
基金
新加坡国家研究基金会;
关键词
Nickel-base alloy; Alloy; 690; STEM; Internal oxidation; Intergranular oxidation; Stress corrosion cracking; NI-BASE ALLOYS; OXIDE-FILMS; INITIATION; MIGRATION; CHROMIUM; BEHAVIOR; STEAM;
D O I
10.1016/j.matchar.2019.109922
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Oxidation testing of Ni-base Alloy 690 was conducted in simulated PWR primary water, and the internal and intergranular (IG) oxidation layers were systematically characterized by analytical transmission electron microscopy to obtain insight into its IG stress corrosion cracking (IGSCC) resistance and behavior. The internal oxidation layer consisted of upper NixFe1-xCr2O4 and innermost Cr2O3. Each internal oxidation layer had a crystallographic orientation relationship with the Alloy 690 matrix, indicating that the layers formed through solid-state reactions between inward diffusing oxygen and the alloying elements. Strong evidence that the Cr2O3 layer formed through the outward grain boundary diffusion of Cr was found, leaving severe Cr depletion along the grain boundary with a steep composition gradient toward the surface. The innermost Cr2O3 layer had a continuous and compact band-shaped morphology around the surface grain boundary. This Cr2O3 layer was revealed to be protective of the inward grain boundary diffusion of oxygen from the surface and therefore responsible for the prevention of grain boundaries from IG oxidation. IG Cr carbides suppressed the internal and IG oxidation further. The key findings obtained in this work may present the main reason for the high resistance of Alloy 690 to IGSCC under PWR normal operating conditions.
引用
收藏
页数:11
相关论文
共 50 条
  • [31] Effect of material chemical composition on oxidation and stress corrosion cracking of the submerged arc welding Alloy 52M overlay in a simulated PWR primary water
    Xu, Xinhe
    Jia, Yibo
    Pan, Deng
    Cui, Tongming
    Lu, Zhanpeng
    Lozano-Perez, Sergio
    Chen, Junjie
    Li, Shuangyan
    Shoji, Tetsuo
    JOURNAL OF NUCLEAR MATERIALS, 2024, 588
  • [32] Assessing the influence of welding-induced mechanics on oxidation and stress corrosion cracking in an Alloy 600-Alloy 152 M weldment under simulated PWR primary water
    Xu, Xinhe
    Pan, Deng
    Li, Entong
    Lu, Zhanpeng
    Cui, Tongming
    Chen, Junjie
    Zheng, Hui
    Li, Kai
    Lozano-Perez, Sergio
    Shoji, Tetsuo
    JOURNAL OF NUCLEAR MATERIALS, 2024, 601
  • [33] A high-resolution characterization of the initiation of stress corrosion crack in Alloy 690 in simulated pressurized water reactor primary water
    Kuang, Wenjun
    Was, Gary S.
    CORROSION SCIENCE, 2020, 163
  • [34] Oxidation products of INCONEL alloys 600 and 690 in pressurized water reactor environments and their role in intergranular stress corrosion cracking
    Ferguson, J. B.
    Lopez, Hugo F.
    METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2006, 37A (08): : 2471 - 2479
  • [35] Oxidation products of INCONEL alloys 600 and 690 in pressurized water reactor environments and their role in intergranular stress corrosion cracking
    J. B. Ferguson
    Hugo F. Lopez
    Metallurgical and Materials Transactions A, 2006, 37 : 2471 - 2479
  • [36] STRESS CORROSION CRACK GROWTH OF ALLOY 52M IN SIMULATED PWR PRIMARY WATER
    Toloczko, M. B.
    Olszta, M. J.
    Bruemmer, S. M.
    15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 2011, : 225 - 243
  • [37] STRESS CORROSION CRACKING OF NICKEL WELD METALS IN PWR PRIMARY WATER
    Xiong Ru
    Zhao Yuxiang
    Liu Guiliang
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 1, 2014,
  • [38] Stress Corrosion Cracking of Nickel Base Alloys in PWR Primary Water
    Guerre, Catherine
    Chaumun, Elizabeth
    Crepin, Jerome
    de Curieres, Ian
    Duhamel, Cecilie
    Heripre, Eva
    Herms, Emmanuel
    Laghoutaris, Pierre
    Molins, Regine
    Sennour, Mohamed
    Vaillant, Francois
    MINOS - MATERIALS INNOVATION FOR NUCLEAR OPTIMIZED SYSTEMS, 2013, 51
  • [39] Microstructural characterization of intergranular stress corrosion cracking of 300 series stainless steels in PWR conditions
    Huang, Y
    Lozano-Perez, S
    Titchmarsh, JM
    Jenkins, ML
    Fujii, K
    ELECTRON MICROSCOPY AND ANALYSIS 2001, 2001, (168): : 203 - 206
  • [40] Bayesian approach for prediction of primary water stress corrosion cracking in Alloy 690 steam generator tubing
    Falaakh, Dayu Fajrul
    Bahn, Chi Bum
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2022, 54 (09) : 3225 - 3234