Electrochemical impedance spectroscopic study of passive zirconium - I. High-temperature, dearated aqueous solutions

被引:57
作者
Ai, Jiahe [1 ]
Chen, Yingzi
Urquidi-Macdonald, Mirna
Macdonald, Digby D.
机构
[1] Penn State Univ, Ctr Electrochem Sci & Technol, Dept Mat Sci & Engn, University Pk, PA 16802 USA
[2] Penn State Univ, Dept Engn Sci & Mech, University Pk, PA 16802 USA
关键词
D O I
10.1149/1.2374946
中图分类号
O646 [电化学、电解、磁化学];
学科分类号
081704 ;
摘要
The development of deterministic models for predicting the accumulation of corrosion damage to zirconium and Zircaloys in boiling water reactor coolant environments requires the acquisition of values for various model parameters. In the present work, the point defect model (PDM) was further developed to account for the properties of passive films comprising oxide barrier layers and porous oxide outer layers that form on zirconium and Zircaloys in high-temperature, deaerated aqueous solutions. The model parameter values were extracted from electrochemical impedance spectroscopic data for zirconium in deaerated, borate buffer solution [0.1 M B(OH)(3) + 0.001 M LiOH, pH 6.94] at 250 degrees C by optimization. The results indicate that the corrosion resistance of zirconium in high-temperature, deaerated aqueous solutions is dominated by the porosity and thickness of the outer layer. The impedance model based on the PDM provides a good account of the growth of the bi-layer passive films described above, and the extracted model parameter values might be used, for example, for predicting the accumulation of general corrosion damage to Zircaloy fuel sheath in BWR operating environments. (c) 2006 The Electrochemical Society.
引用
收藏
页码:C43 / C51
页数:9
相关论文
共 41 条
[1]  
Ai JH, 2007, J ELECTROCHEM SOC, V154, pC52, DOI 10.1149/1.2374947
[2]  
Anada H, 1996, ZIRCONIUM NUCL IND 1, P35
[3]  
[Anonymous], 1998, IAEATECDOC996
[4]  
[Anonymous], 1993, IAEA-TECDOC-684 Corrosion of Zirconium Alloys in Nuclear Power
[5]   Characterization of Zircaloy-4 oxide layers by impedance spectroscopy [J].
Barberis, P ;
Frichet, A .
JOURNAL OF NUCLEAR MATERIALS, 1999, 273 (02) :182-191
[6]  
BEIE HJ, 1994, AM SOC TEST MATER, V1245, P615, DOI 10.1520/STP15212S
[7]   The transpassive dissolution mechanism of highly alloyed stainless steels I.: Experimental results and modelling procedure [J].
Betova, I ;
Bojinov, M ;
Laitinen, T ;
Mäkelä, K ;
Pohjanne, P ;
Saario, T .
CORROSION SCIENCE, 2002, 44 (12) :2675-2697
[8]  
BOJINOV M, 2005, J ASTM INT, V2, P1
[9]   Study of the mechanisms controlling the oxide growth under irradiation: Characterization of irradiated Zircaloy-4 and Zr-1Nb-O oxide scales [J].
Bossis, P ;
Thomazet, J ;
Lefebvre, F .
ZIRCONIUM IN THE NUCLEAR INDUSTRY: THIRTEENTH INTERNATIONAL SYMPOSIUM, 2002, 1423 :190-217
[10]   A POINT-DEFECT MODEL FOR ANODIC PASSIVE FILMS .3. IMPEDANCE RESPONSE [J].
CHAO, CY ;
LIN, LF ;
MACDONALD, DD .
JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 1982, 129 (09) :1874-1879