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
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