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http://dx.doi.org/10.14773/cst.2012.11.3.096

Effect of Lead Concentration on Surface Oxide Formed on Alloy 600 in High Temperature and High Pressure Alkaline Solutions  

Kim, Dong-Jin (Nuclear Materials Division, Korea Atomic Energy Research Institute)
Kim, Hyun Wook (Nuclear Materials Division, Korea Atomic Energy Research Institute)
Moon, Byung Hak (Nuclear Materials Division, Korea Atomic Energy Research Institute)
Kim, Hong Pyo (Nuclear Materials Division, Korea Atomic Energy Research Institute)
Hwang, Seong Sik (Nuclear Materials Division, Korea Atomic Energy Research Institute)
Publication Information
Corrosion Science and Technology / v.11, no.3, 2012 , pp. 96-102 More about this Journal
Abstract
Outer diameter stress corrosion cracking (ODSCC) has occurred for Alloy 600 (Ni 75 wt%, Cr 15 wt%, Fe 10 wt%) as a heat exchanger tube of the steam generator (SG) in nuclear power plants (NPP) during long term operation. Among many causes for SCC, lead (Pb) is known to be one of the most deleterious species in the secondary system. In the present work, the oxide formed on Alloy 600 was characterized as a function of the PbO content in 0.1 M NaOH at $315^{\circ}C$ by using an electrochemical impedance spectroscopy (EIS), a transmission electron microscopy (TEM), equipped with an energy dispersive x-ray spectroscopy (EDS). The oxide property was analyzed in view of SCC susceptibility.
Keywords
alloy 600; SCC; lead; oxide;
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  • Reference
1 A. Baum, K. Evans: Proc. of 12th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Salt Lake City, Utah, Aug. 1-5, p. 1155 (2005).
2 J. M. Sarver: EPRI Workshop on Intergranular Corrosion and Primary Water Stress Corrosion Cracking Mechanisms, NP-5971, EPRI, Palo Alto, p. C11/1 (1987).
3 M. L. Castano-Marin, D. Gomez-Briceno and F. Hernandez- Arroyo: Proc. of 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, San Diego, CA, Aug. 1-5, p. 189 (1993).
4 M. D. Wright and M. Mirzai: Proc. of 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Newport Beach, CA, Aug. 1-5, p. 657 (1999).
5 R. W. Staehle: Proc. of 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Stevenson, WA, Aug. 10-14, p. 381 (2003).
6 A. J. Bard and L. R. Faulkner: Electrochemical Methods, Fundamentals and Applications, John Wiley & Sons, p. 323 (1980).
7 C. Gabrielli, Identification of Electrochemical Processes by Frequency Response Analysis, Technical report number 004/83, p. 76 (1983).
8 HSC Chemistry Database, 6.0.
9 MULTEQ calculation performed at ANL (2008).
10 NUREG report, NUREG/CP-0189 (2003).