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Factors in the Selection of Container Materials for the Disposal of HLW/SF

Published online by Cambridge University Press:  27 March 2012

Fraser King
Fraser King*
Affiliation:
Integrity Corrosion Consulting Ltd, Nanaimo, BC, Canada V9T 1K2
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Abstract

The container is the only absolute barrier in the multi-barrier system that forms the basis of all nuclear waste disposal strategies. The selection of an appropriate container material is therefore of utmost importance. Some of the factors that underlay the choice of container material are discussed, ranging from the properties of the near-field and host rock to the desired or expected containment period.

There has been a trend towards the specification of container materials that will corrode actively under repository conditions, such as copper and carbon steel. Passive materials, such as titanium and nickel alloys and the various stainless steels, have found less acceptance and the reasons for this emphasis on active materials are also discussed.

In selecting an appropriate container material, it is essential to understand the nature of the corrosive environment and how it evolves over time. The evolution of environmental conditions will also cause the corrosion behaviour of the container to change with time. For repositories in saturated environments, it will be argued that passive alloys can provide long container lifetimes without some of the disadvantages of some active materials such as gas generation and other adverse impacts on other barriers.

Finally, areas of future development and areas requiring additional study will be discussed.

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1475: Symposium NW – Scientific Basis for Nuclear Waste Management XXXV , 2012 , imrc11-1475-nw35-il05
Copyright
Copyright © Materials Research Society 2012

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References

REFERENCES

1 Shoesmith, D. W., Corrosion, 62, 703–722 (2006).10.5006/1.3278296Google Scholar
2 Kursten, B., Smailos, E., Azkarate, I., Werme, L., Smart, N.R., Santarini, G., COBECOMA, State-of-the-art Document on the COrrosion BEhaviour of COntainer Materials. European Commission, Contract N° FIKW-CT-20014–20138 Final Report (2004).Google Scholar
3 King, F. and Shoesmith, D. W., in ‘Geological repository systems for safe disposal of spent nuclear fuels and radioactive waste’, (ed. Ahn, J. and Apted, M. J.), Chap. 13; 2010, Oxford, Woodhead Publishing.Google Scholar
4 King, F. and Padovani, C., Corros. Eng. Sci. Technol. 46, 82–90 (2011).10.1179/1743278211Y.0000000005Google Scholar
5 SKB, Long-term safety for the final repository for spent nuclear fuel at Forsmark. Main Report of the SR-Site project, Swedish Nuclear Fuel and Waste Management Company Report, Technical Report TR-11–01 (2011).Google Scholar
6 Posiva, Expected evolution of a spent nuclear fuel repository at Olkiluoto, Posiva Report 2006–05, revised October 2007.Google Scholar
7 Sridhar, N. and Cragnolino, G.A., Corrosion, 49, 967–976 (1993).10.5006/1.3316024Google Scholar
8 King, F., Lilja, C., Pedersen, K., Pitkänen, P., and Vähänen, M., An update of the state-of-the-art report on the corrosion of copper under expected conditions in a deep geologic repository. Swedish Nuclear Fuel Supply Company Report SKB TR-10-67, Posiva Oy Report POSIVA 2011-01 (2011).Google Scholar
9 Yucca Mountain Repository License Application, DOE/RW-0573, US Department of Energy, 2008.Google Scholar
10 Hua, F., Mon, K., Pasupathi, P., Gordon, G. and Shoesmith, D., Corrosion, 61, 987–1003 (2005).10.5006/1.3280899Google Scholar
11 Smart, N. R. and Wood, P., Corrosion resistance of stainless steel radioactive waste packages, Nirex report no. N/110, UK Nirex Limited, Didcot, UK, 2004.Google Scholar
12 Sridhar, N., Cragnolino, G.A., and Dunn, D., Experimental investigations of localized corrosion of high-level container materials. Center for Nuclear Waste Regulatory Analyses, CNWRA 93‑004 (1993).Google Scholar
13 McMurray, J., Dixon, D.A., Garroni, J.D., Ikeda, B.M., Stroes‑Gascoyne, S., Baumgartner, P., and Melnyk, T.W., Evolution of a Canadian deep geologic repository: base scenario. Ontario Power Generation, Nuclear Waste Management Division Report 06819‑REP‑01200‑10902‑R00 (2003).Google Scholar
14 Féron, D., Crusset, D., and Gras, J.-M., Corrosion 65, 213‑223 (2009).10.5006/1.3319129Google Scholar
15 JNC, H12: Project to establish the scientific and technical basis for HLW disposal in Japan. Japan Nuclear Cycle Development Institute, Supporting Report 2, Repository Design and Engineering Technology (2000).Google Scholar
16 Johnson, L.H. and King, F., J. Nucl. Mater., 379, 9‑15 (2008).10.1016/j.jnucmat.2008.06.003Google Scholar
17 Kursten, B. and Druyts, F., J. Nucl. Mater. 379, 91‑96 (2008).10.1016/j.jnucmat.2008.06.020Google Scholar
18 King, F., Corrosion, 65, 233‑251 (2009).10.5006/1.3319131Google Scholar
19 King, F. and Watson, S., Review of the performance of selected metals as canister materials for UK spent fuel and/or HLW, Quintessa Limited report no. QRS-1384J-1, version 2.1, 2010.Google Scholar
20 King, F., Kolar, M., Vähänen, M. and Lilja, C., Corros. Eng. Sci. Technol., 46, 217–222 (2011).10.1179/18211Y.0000000004Google Scholar
21 Carlson, L., Karnland, O., Olsson, S., Rance, A., and Smart, N., Experimental studies on the interactions between anaerobically corroding iron and bentonite. Posiva Working Report 2006-60 (2006).Google Scholar
22 Nagra, Effects of post-disposal gas generation in a repository for spent fuel, high-level waste and long-lived intermediate level waste sited in Opalinus Clay. Nagra Technical Report NTB 04–06 (2004).Google Scholar
23 Mon, K.G., Gordon, G.M., and Rebak, R.B., in Proc. 12th Int. Conf. Environmental Degradation of Materials in Nuclear Power System – Water Reactors, Allen, T.R., King, P.J., and Nelson, L. (eds.), The Minerals, Metals & Materials Society (Warrendale, PA), p. 1431–1438 (2005).Google Scholar
24 Kojima, Y., Hioki, T., and Tsujikawa, S., Mat. Res. Soc. Symp. Proc., 353, 711–718 (1995).10.1557/PROC-353-711Google Scholar
25 Taniguchi, N., in Prediction of Long Term Corrosion Behaviour in Nuclear Waste Systems. European Federation of Corrosion Publication No. 36 (Institute of Materials, Minerals and Mining, London), p. 424–438 (2003).Google Scholar