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A Review of Corrosion Considerations of Container Materials Relevant to Underground Disposal of High-Level Radioactive Waste in Belgium

Published online by Cambridge University Press:  21 March 2011

Bruno Kursten  and
Frank Druyts
Bruno Kursten
Affiliation:
SCK•CEN, The Belgian Nuclear Research Centre Waste and Disposal Department Boeretang 200 B-2400 Mol, Belgium
Frank Druyts
Affiliation:
SCK•CEN, The Belgian Nuclear Research Centre Waste and Disposal Department Boeretang 200 B-2400 Mol, Belgium
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Abstract

The underground formation that is currently being considered in Belgium for the permanent disposal of high-level radioactive waste and spent fuel is a 30-million-year-old argillaceous sediment (Boom Clay layer). This layer is located in the northeast of Belgium and extending under the Mol-Dessel nuclear site at a depth between 180 and 280 meter.

Within the concept for geological disposal (multibarrier system), the metallic container is the primary engineered barrier. Its main goal is to contain the radioactive waste and to prevent the groundwater from coming into contact with the wasteform by acting as a tight barrier. The corrosion resistance of container materials is an important aspect in ensuring the tightness of the metallic container and therefore plays an important role in the safe disposal of HLW. The metallic container has to provide a high integrity, i.e. no through-the-wall corrosion should occur, at least for the duration of the thermal phase (500 years for vitrified HLW and 2000 years for spent fuel).

An extensive corrosion evaluation programme, sponsored by the national authorities and the European Commission, was started in Belgium in the mid 1980's. The main objective was to evaluate the long-term corrosion performance of a broad range of candidate container materials. In addition, the influence of several parameters, such as temperature, oxygen content, groundwater composition (chloride, sulphate and thiosulphate), γ-radiation, … were investigated. The experimental approach consisted of in situ experiments (performed in the underground research facility, HADES), electrochemical experiments, immersion experiments and large scale demonstration tests (OPHELIE, PRACLAY). Degradation modes considered included general corrosion, localised corrosion (pitting) and stress corrosion cracking.

This paper gives an overview of the more relevant experimental results, gathered over the past 25 years, of the Belgian programme in the field of container corrosion.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 932: Symposium – Scientific Basis for Nuclear Waste Management XXIX , 2006 , 33.1
Copyright
Copyright © Materials Research Society 2006

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References

REFERENCES

1. ElBaradei, M., “Nuclear Power: An Evolving Scenario,” IAEA Bulletin 46(1), p. 7 (2004).Google Scholar
2. Kursten, B. and Druyts, F., “Corrosion of Several Sensors Originating from the OPHELIE Mock-up Experiment,” EUROCORR2005, paper no. 493 (in press).Google Scholar
3. Bel, J. and Gens, R. CSNI/RILEM Workshop on Use and Performance of Concrete in NPP Fuel Cycle Facilities, 15-16 March 2004, Madrid, Spain (2004).Google Scholar
4. ONDRAF/NIRAS, “SAFIR 2 – Safety Assessment and Feasibility Interim Report 2, Chapter 4: Design of the repository,” (ONDRAF/NIRAS, Brussels, Belgium, 2001).Google Scholar
5. Neerdael, B. and Volckaert, G., in Geological Challenges in Radioactive Waste Isolation – Third Worldwide Review, edited by Witherspoon, P.A. and Bodvarsson, G.S. (Ernest Orlando Lawrence Berkeley National Laboratory, Berkeley, CA, 2001), pp. 47–54.Google Scholar
6. Kursten, B., Smailos, E., Azkarate, I., Werme, L., Smart, N.R., Marx, G., Cuñado, M.A. and Santarini, G., Proceedings of the Sixth European Commission Conference on the Management and Disposal of Radioactive Waste (EURADWASTE'04), ed. Davies, C. (European Commission, 2004), pp. 185–195.Google Scholar
7. Kursten, B., Smailos, E., Azkarate, I., Werme, L., Smart, N.R. and Santarini, G., “COBECOMA: State-of-the-art Document on the Corrosion Behaviour of Container Materials,” (in press).Google Scholar
8. Volckaert, G. and Mallants, D., Workshop Proceedings on Gas Generation and Migration in Radioactive Waste Disposal (OECD Nuclear Energy Agency, Paris, France, 2001), pp. 125–128.Google Scholar
9. Sedriks, A.J., “Corrosion of Stainless Steels, 2nd edition,” (Wiley-Interscience, New York, USA, 1996).Google Scholar
10. Szklarska-Smialowska, Z., “Pitting Corrosion of Metals,” (NACE, Houston, Texas, USA, 1986).Google Scholar