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Experimental Investigation of Passivation Behavior and Corrosion Rate of Carbon Steel in Compacted Bentonite

Published online by Cambridge University Press:  10 February 2011

N. Taniguchi
Affiliation:
Power Reactor and Nuclear Fuel Development Corporation, Tokai-mura, Ibaraki 319-11, JAPAN
A. Honda
Affiliation:
Power Reactor and Nuclear Fuel Development Corporation, Tokai-mura, Ibaraki 319-11, JAPAN
H. Ishikawa
Affiliation:
Power Reactor and Nuclear Fuel Development Corporation, Tokai-mura, Ibaraki 319-11, JAPAN
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Abstract

Carbon steel is one of the candidate materials for overpacks for high-level radioactive waste disposal in Japan. Passivation behavior and corrosion rate of carbon steel were investigated by electrochemical measurements under simulated repository conditions. The results of the anodic polarization measurements showed that carbon steel was hard to passivate in highly compacted bentonite. Therefore, general corrosion seems to be most probable in repository conditions. In order to monitor the in-situ general corrosion rate in compacted bentonite, the AC impedance of carbon steel was measured under aerated conditions. It was confirmed that the corrosion rate in saturated bentonite decreased with time and it was almost the same as that observed in deaerated aqueous conditions. The corrosion rate did not increase in the presence of corrosion products formed by external current supply.

Type
Research Article
Copyright
Copyright © Materials Research Society 1998

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References

REFERENCES

[1] Ishikawa, H., Honda, A, Tsurudome, K., Inoue, K., Obata, M., N.Sasaki, PNC TN8410 92-139 (1992)Google Scholar
[2] Marsh, G.P. and Taylor, K.J., Corros. Sci. 28, 3 (1988), pp289320.Google Scholar
[3] Power Reactor and Nuclear Fuel Development Corporation, PNC TN1410 93-059 (1992)Google Scholar
[4] Marsh, G.P., Blend, I.W., Desport, J.A., Naish, C., Westcott, C. and Taylor, K.J., European Appl. Res. Rept.-Nucl. Sci. Technol. 5.2 (1983), pp.223252 Google Scholar
[5] Honda, A., Taniguchi, N., Ishikawa, H., Hoch, A.R., Porter, F.M. and Sharland, S.M., in Proceedings of International Symposium on Plant Aging and Life Predictions of Corrodible Structures (Houston, TX: NACE International 1995), pp. 217226.Google Scholar
[6] Kojima, Y., Hioki, T. and Tsujikawa, S., in Scientific Basis for Nuclear Waste Management XVIII, ed. by Murakami, T. and Ewing, R.C., (Pittsburgh, PA : MRS, 1994), pp.711718.Google Scholar
[7] Noda, K., Hirota, Y. and Seo, M., in Proceedings of International Symposium on Plant Aging and Life Predictions of Corrodible Structures (Houston, TX : NACE International 1995), pp.771776.Google Scholar
[8] Tobe, Y., Nishikata, A., Tsuru, T., in Proceeding of Japan Corrosion Conference '95 Paper C-312 (1995)Google Scholar
[9] Wieland, E., Wanner, H., Albinsson, Y., Wersin, P. and Karnland, O., SKB Technical Report 94-26 (1994)Google Scholar
[10] Taniguchi, N., Honda, A. and Ishikawa, H., in Proceeding of 43d Japan Corrosion Conference, Paper A-303 (1996)Google Scholar