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Comparison of in Situ and Laboratory Corrosion Experiments with Borosilicate Nuclear Waste Glass

Published online by Cambridge University Press:  25 February 2011

Werner Lutze  and
Rodney C. Ewing
Werner Lutze
Affiliation:
Kernforschungszentrum Karlsruhe, Germany
Rodney C. Ewing
Affiliation:
University of New Mexico, Albuquerque, New Mexico 87131, USA
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Abstract

The comparison of laboratory data from the corrosion of borosilicate nuclear waste glass (German SM513LW11 and French R7T7) with data from the Materials Interface Interactions Test (MIIT) and Repository Systems Simulation Test (RSST) illustrates the inherent limitations of in situ tests. Although in situ tests may confirm the short term behavior of waste forms and identify phenomena associated with the repository system, they do not provide the fundamental basis for the extrapolation of long-term behavior.

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Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 257: Symposium – Scientific Basis for Nuclear Waste Management XV , 1991 , 127
Copyright
Copyright © Materials Research Society 1992

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References

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