Effect of dissolved hydrogen on the electrochemical behaviour of Alloy 600 in simulated PWR primary water at 290°C

被引:60
作者
Qiu, Yubing [1 ,2 ]
Shoji, Tetsuo [1 ]
Lu, Zhanpeng [1 ]
机构
[1] Tohoku Univ, Fracture & Reliabil Res Inst, Sendai, Miyagi 9808579, Japan
[2] Huazhong Univ Sci & Technol, Sch Chem & Chem Engn, Wuhan 430074, Hubei, Peoples R China
关键词
Alloy; EIS; Polarization; High temperature corrosion; Passivity; HIGH-TEMPERATURE WATER; NICKEL-BASED ALLOYS; REVISED POURBAIX-DIAGRAMS; 316L STAINLESS-STEEL; HIGH-PRESSURE WATER; OXIDE-FILMS; AQUEOUS ENVIRONMENTS; CORROSION BEHAVIOR; PASSIVE FILMS; BASE ALLOYS;
D O I
10.1016/j.corsci.2011.02.020
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
With an increase in dissolved hydrogen (DH) content from 0 to 5 cm(3) STP H(2)/kg H(2)O the electrochemical behaviour of Alloy 600 in deaerated PWR primary water at 290 degrees C was investigated, using corrosion potential (E(corr)) monitoring, potentiodynamic polarization, cyclic voltammetry and electrochemical impedance spectroscopy (EIS). DH content controls the E(corr), of Alloy 600. Raising DH content directly promotes the cathodic process and reduces the passivity of Alloy 600 significantly. EIS results show that increasing DH content results in a thinner inner-layer oxide film and ions diffusion becomes easier. The mechanism of these DH effects is discussed. (C) 2011 Elsevier Ltd. All rights reserved.
引用
收藏
页码:1983 / 1989
页数:7
相关论文
共 50 条
  • [1] Effects of temperature and pH on the electrochemical behaviour of alloy 600 in simulated pressurized water reactor primary water
    Yang, Jie
    Li, Yanhui
    Macdonald, Digby D.
    JOURNAL OF NUCLEAR MATERIALS, 2020, 528
  • [2] Influence of dissolved hydrogen on oxide film and PWSCC of Alloy 600 in PWR primary water
    Nakagawa, T
    Totsuka, N
    Terachi, T
    Nakajima, N
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2003, 40 (01) : 39 - 43
  • [3] Effect of dissolved hydrogen concentration in simulated PWR primary water on stress corrosion cracking susceptibility of ni-based alloy at 290°C and 320°C
    Kobayashi T.
    Yonezawa T.
    Dozaki K.
    Hisamune K.
    Sugino W.
    Sato K.
    Transactions of the Atomic Energy Society of Japan, 2016, 15 (01) : 21 - 31
  • [4] Effect of temperature and dissolved hydrogen on oxide films formed on Ni and Alloy 182 in simulated PWR water
    Mendonca, R.
    Bosch, R. -W.
    Van Renterghem, W.
    Vankeerberghen, M.
    de Araujo Figueiredo, C.
    JOURNAL OF NUCLEAR MATERIALS, 2016, 477 : 280 - 291
  • [5] X-ray absorption study of oxide film formed on Alloy 600 in PWR primary water at 290°C with a decreased concentration of dissolved hydrogen
    Kakitani, Kenta
    Kobayashi, Takaaki
    Abe, Hiroaki
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2024, 61 (03) : 397 - 402
  • [6] 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.
    CORROSION SCIENCE, 2023, 221
  • [7] The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen
    Chen, Junjie
    Lu, Zhanpeng
    Meng, Fanjiang
    Xu, Xuelian
    Xiao, Qian
    Kim, Ho-Sub
    Jang, Changheui
    JOURNAL OF NUCLEAR MATERIALS, 2019, 517 : 179 - 191
  • [8] Effect of dissolved hydrogen on corrosion of Inconel Alloy 600 in high temperature hydrogenated water
    Peng, Qunjia
    Hou, Juan
    Sakaguchi, Kazuhiko
    Takeda, Yoichi
    Shoji, Tetsuo
    ELECTROCHIMICA ACTA, 2011, 56 (24) : 8375 - 8386
  • [9] Study on electrochemical behavior of 690 alloy with corrosion products in simulated PWR primary water environment
    Cheng, Xuequn
    Zuo, Xiao Mei
    ANTI-CORROSION METHODS AND MATERIALS, 2018, 65 (06) : 616 - 625
  • [10] EFFECT OF PARTIAL-PRESSURE OF HYDROGEN ON IGSCC OF ALLOY 600 IN PWR PRIMARY WATER
    REBAK, RB
    SZKLARSKASMIALOWSKA, Z
    CORROSION, 1991, 47 (10) : 754 - 757