Electrochemical Interpretation of a Stress Corrosion Cracking of Thermally Treated Ni Base Alloys in a Lead Contaminated Water

Author:

Hwang Seong Sik1,Lim Yun Soo1,Kim Hong Pyo1,Kim Joung Soo1,Thomas Larry2

Affiliation:

1. Korea Atomic Energy Research Institute

2. Pacific Northwest National Laboratory

Abstract

Since the PbSCC(Lead stress corrosion cracking) of alloy 600 tubing materials was reported by Copson and Dean in 1965, the effect of lead on a corrosion film and cracking morphology have been continually debated. An electrochemical interaction of lead with the alloying elements of SG tubings was studied and the corrosion products were analyzed. It was found that lead enhanced the anodic dissolution of alloy 600 and alloy 690 in the electrochemical test. The lead preferentially dissolved the Cr from the corrosion film of alloy 600 and alloy 690 in alkaline water. The lead ion seemed to penetrate into the TG crack tip and react with the corrosion film. A selective Cr depletion was observed to weaken the stability of the passive film on the alloys. Whereas passivity of Ni became stable in lead containing solution, Cr and Fe passivity became unstable.

Publisher

Trans Tech Publications, Ltd.

Subject

Condensed Matter Physics,General Materials Science,Atomic and Molecular Physics, and Optics

Reference13 articles.

1. B.P. Miglin, J.M. Sarver, Preliminary studies of lead stress corrosion cracking of Alloy 690", Proc. of the 4th Int, l Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, pp.7-18, Jekyll Island, Georgia, USA, Aug. 6-10, (1989).

2. S.S. Hwang, H.P. Kim, D.H. Lee, U.C. Kim, J.S. Kim, Corrosion behavior of Ni-base alloys in lead contaminated water, Proc. of the Contributions of materials investigation to the resolution of problems encountered in pressurized water reactors, Vol. 1, pp.403-415, Fontevraud IV, France, Sept. 14-18, (1998).

3. S. S Hwang, U.C. Kim, Journal of nuclear materials, 246 (1997) : p.77.

4. S. S Hwang, H.P. Kim, D.H. Lee, U.C. Kim, J.S. Kim, Journal of nuclear materials, 275 (1999) : p.28.

5. T. Sakai, T. Senjuh, K. Aoki, T. Shigemitsu, Y. Kishi, Lead induced stress corrosion cracking of Alloy 600 and 690 in high temperature water", Proc. of the 5th Int, l Symposium on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, pp.764-772, Monterey, California, USA, Aug. 25-29, (1991).

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