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Corrosion Considerations Related to Carbon Steel Radioactive Waste Packages Exposed to Cementitious Materials

Published online by Cambridge University Press:  20 February 2017

Bruno Kursten ,
Frank Druyts ,
Nick R. Smart ,
Digby D. Macdonald  and
Robert Gens
Bruno Kursten*
Affiliation:
SCK•CEN, The Belgian Nuclear Research Centre, R&D Waste Packages Unit, Boeretang 200, 2400 Mol, Belgium
Frank Druyts
Affiliation:
SCK•CEN, The Belgian Nuclear Research Centre, R&D Waste Packages Unit, Boeretang 200, 2400 Mol, Belgium
Nick R. Smart
Affiliation:
Amec Foster Wheeler, Clean Energy, Building 150, Harwell Oxford, Didcot, Oxfordshire, OX11 0QB, U.K.
Digby D. Macdonald
Affiliation:
University of California at Berkeley, Department of Materials, Science and Engineering, Berkeley, CA 94720, U.S.A.
Robert Gens
Affiliation:
ONDRAF/NIRAS, The Belgian Agency for Radioactive Waste and Enriched Fissile Materials, Avenue des Arts 14, 1210 Brussels, Belgium
*
*(Email: [email protected])
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Abstract

The Supercontainer is the reference concept for the post-conditioning of vitrified high-level radioactive waste and spent fuel in Belgium. It consists of a prefabricated concrete buffer that completely surrounds a carbon steel overpack. In this highly alkaline environment (pH ∼ 13.6) and under normal conditions (i.e. without the ingress of aggressive species), the carbon steel overpack will be protected by a passive oxide film, which is believed to result in very low uniform corrosion rates.

This paper gives an overview of the status of the uniform corrosion, pitting corrosion and stress corrosion cracking behaviour of carbon steel expected during the waste disposal period.

Keywords

Corrosionsteelwaste management
Type
Articles
Information
MRS Advances , Volume 1 , Issue 63-64: Scientific Basis for Nuclear Waste Management XXXIX , 2016 , pp. 4193 - 4199
Copyright
Copyright © Materials Research Society 2017 

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References

REFERENCES

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