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Characterization of the Surface of the HLW Glass R7T7 Reacted in Salt Brines

Published online by Cambridge University Press:  26 February 2011

H. Roggendorf ,
R. Conradt  and
H. Schmidt
H. Roggendorf
Affiliation:
Fraunhofer-Institut für Silicatforschung, Neunerplatz 2, D-8700 Würzburg, Federal Republic of, Germany
R. Conradt
Affiliation:
now: Department of Materials Science, Faculty of Science, Chulalongkorn University, Bangkok 10500, Thailand
H. Schmidt
Affiliation:
Fraunhofer-Institut für Silicatforschung, Neunerplatz 2, D-8700 Würzburg, Federal Republic of, Germany
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Abstract

Borosilicate glasses are proposed as waste form for the final disposal of High Level Waste (HLW) in salt formations by the Federal Republic of Germany. To check the safety of this waste form the corrosion of the non-radioactive borosilicate glass R7T7 in salt brines has been studied in collaboration with the Hahn-Meitner-Institut, Berlin. Temperatures up to 190°C and S/V ratios (surface area to solution volume ratio) between 3.3 and 1000 m were applied. S/V was varied by the addition of glass powder. The results presented here concern the characterization of the surface composition of the corroded glass (corroded at 190°C in a brine containing high amounts of MgCl-, called Q brine in this paper) after removing the reaction product layer. The corrosion conditions were chosen to obtain samples typical of long term (silica saturation) corrosion. The surface composition was analyzed quantitatively by X-ray photoelectron spectroscopy (XPS) by using external standard glasses with a composition similar to R7T7. Additionally scanning electron microscopy (SEM) was employed.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 127: Symposium BERLIN – Scientific Basis for Nuclear Waste Management XII , 1988 , 89
Copyright
Copyright © Materials Research Society 1989

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References

REFERENCES

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