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Statistically Designed Lead Corrosion Experiments for Nuclear Waste Disposal

Published online by Cambridge University Press:  28 February 2011

P. Mani Mathew  and
P.A. Krueger
P. Mani Mathew
Affiliation:
AECL Research, Whiteshell Laboratories, Pinawa, Manitoba, Canada ROE 1LO
P.A. Krueger
Affiliation:
AECL Research, Whiteshell Laboratories, Pinawa, Manitoba, Canada ROE 1LO
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Abstract

This paper describes galvanic corrosion studies of lead, a candidate matrix metal, coupled vith ASTM Grade-2 titanium, a candidate container-shell material, to determine the barrier-lifetime for a lead matrix container - one container concept considered in the Canadian Nuclear Fuel Waste Management Program. In these studies the fractional factorial statistical design of Box-Behnken was used to develop mathematical relationships between the independent variables and the corrosion rate of lead.

Using the mathematical expressions derived in this study, the additional barrier-lifetime that a 25-mm-thick lead layer could provide to a titanium container, which eventually perforates by corrosion, was calculated to be at least 3500 years.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 212: Symposium P – Scientific Basis for Nuclear Waste Management XIV , 1990 , 327
Copyright
Copyright © Materials Research Society 1991

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References

REFERENCES

1 Nuttall, K., Crosthwaite, J.L., McKay, P., Mathew, P.M., Teper, B., Maak, P.Y.Y. and Moles, M.D.C.. 1983.Google Scholar
The Canadian Container Development Program for Fuel Isolation. Materials Research Society Symposia Proceedings 15 (Scientific Basis for Nuclear Waste Management VI), 677–684.Google Scholar
2 Mathew, P.M., Nadeau, J.S., Weinberg, F., Chaklader, A.C.D. and Nuttall, K.. Investment of Irradiated Reactor Fuel in a Metal Matrix, Canadian Metallurgical Quarterly 22 (1), 107–115 (1983).CrossRefGoogle Scholar
3 Mathew, P.M.. 1987. Metal Matrices for Nuclear Fuel Waste Disposal. In The Geological Disposal of High Level Radioactive Wastes, 315–347, edited by Brookins, D., Theophrastus Publications, S.A. Zographou, Athens, Greece.Google Scholar
4 Mathew, P.M. and Krueger, P.A., Galvanic Corrosion of Lead Coupled with Titanium for Nuclear Fuel Waste Disposal, Canadian Metallurgical Quarterly, 28, 89–99 (1989).CrossRefGoogle Scholar
5 Dixon, D.A., Gray, M.N., Baumgartner, P. and Rigby, G.L.. Pressures Acting on Waste Containers in Bentonite-Based Materials, Proceedings of the Canadian Nuclear Society 2nd International Conference on Radioactive Management, Winnipeg, Manitoba, Canada, pp. 221–227, 1986 Sept.Google Scholar