Passivity degradation of nuclear steam generator tubing alloy induced by Pb contamination at high temperature

被引:27
|
作者
Lu, B. T. [1 ]
Luo, J. L. [1 ]
Lu, Y. C. [2 ]
机构
[1] Univ Alberta, Dept Chem & Mat Engn, Edmonton, AB T6G 2G6, Canada
[2] Atom Energy Canada Ltd, Chalk River Labs, Chalk River, ON K0J 1J0, Canada
基金
加拿大自然科学与工程研究理事会;
关键词
STRESS-CORROSION CRACKING; POINT-DEFECT MODEL; IN-SITU STM; ACID-SOLUTION; BASE ALLOYS; FILMS; HYDROGEN; IRON; SURFACE; NICKEL;
D O I
10.1016/j.jnucmat.2012.06.021
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Effects of Pb contamination on the passivity of a Ni-based alloy (UNS N06690) in a simulated crevice chemistry of steam generator with near-neutral pH at 300 degrees C are elucidated using electrochemical measurements and surface analysis techniques. The experimental observations reveal that Pb impurity can enter anodic film, which results in substantial changes in the films structure via hindering the dehydration during the passivation and retarding the formation of spinel oxides. The presence of Pb-contamination can also increase hydrogen content in anodic film. Finally, the mechanism of passivity degradation induced by Pb contamination is described on the basis of the experimental data and established theory. (C) 2012 Elsevier B.V. All rights reserved.
引用
收藏
页码:305 / 314
页数:10
相关论文
共 50 条
  • [31] EFFECT OF BORIC-ACID ON PIT GROWTH IN ALLOY-600 STEAM-GENERATOR TUBING
    WAS, GS
    CHOI, D
    CORROSION, 1992, 48 (02) : 103 - 113
  • [32] 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
  • [33] DEGRADATION OF ALLOY 800 UNDER STEAM GENERATOR SECONDARY SIDE CREVICE CONDITIONS
    Lu, Y. C.
    Goszczynski, G.
    Ramamurthy, S.
    ICONE 17: PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 1, 2009, : 649 - 657
  • [34] Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water
    Tan, Jibo
    Wu, Xinqiang
    Han, En-Hou
    Ke, Wei
    Liu, Xiaoqiang
    Meng, Fanjiang
    Xu, Xuelian
    CORROSION SCIENCE, 2014, 89 : 203 - 213
  • [35] EVALUATION OF CREEP PROPERTIES OF ALLOY 690 STEAM GENERATOR TUBES AT HIGH TEMPERATURE USING TUBE SPECIMEN
    Kim, Jongmin
    Kim, Woogon
    Kim, Minchul
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2019, VOL 6B, 2019,
  • [36] Secondary side corrosion of French PWR steam generator tubing: Contribution of surface analyses to the understanding of the degradation process
    Boursier, JM
    Dupin, M
    Gosset, P
    Rouillon, Y
    PROCEEDINGS OF THE NINTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 1999, : 555 - 563
  • [37] DEVELOPMENT OF STEAM-GENERATOR TUBING MATERIALS .1. IMPROVEMENT OF RESISTANCE TO IGSCC OF ALLOY-800
    NAKAYAMA, T
    TETSU TO HAGANE-JOURNAL OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1985, 71 : 1315 - 1315
  • [38] Sulfur induced corrosion (SIC) mechanism of steam generator (SG) tubing at micro scale: A critical review
    Xia, Da-Hai
    Wang, Jianqiu
    Qin, Zhenbo
    Gao, Zhiming
    Wu, Zhong
    Wang, Jihui
    Yang, Lixia
    Hu, Wenbin
    Luo, Jing-Li
    MATERIALS CHEMISTRY AND PHYSICS, 2019, 233 : 133 - 140
  • [39] DEVELOPMENT OF THE HIGH TEMPERATURE FRETTING WEAR SIMULATOR FOR STEAM GENERATOR
    Lee, Choon Yeol
    Kim, Joong Ho
    Bae, Joon Woo
    Chai, Young Suck
    INTERNATIONAL JOURNAL OF MODERN PHYSICS B, 2010, 24 (15-16): : 2603 - 2608
  • [40] Environmentally Assisted Fatigue Evaluation Model of Alloy 690 Steam Generator Tube in High-Temperature Water
    Tan, Jibo
    Liu, Xiaoqiang
    Xu, Xuelian
    Han, En-Hou
    Wu, Xinqiang
    Wang, Xiang
    CORROSION, 2016, 72 (05) : 655 - 664