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High-Level Waste Glass Compendium; What it Tells us Concerning the Durability of Borosilicate Waste Glass

Published online by Cambridge University Press:  25 February 2011

J. C. Cunnane  and
J. M. Allison
J. C. Cunnane
Affiliation:
Argonne National Laboratory, Argonne, IL
J. M. Allison
Affiliation:
U.S. Department of Energy, EM-343, Washington, D.C.
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Abstract

Facilities for vitrification of high-level nuclear waste in the United States are scheduled for startup in the next few years. It is, therefore, appropriate to examine the current scientific basis for understanding the corrosion of high-level waste borosilicate glass for the range of service conditions to which the glass products from these facilities may be exposed. To this end, a document has been prepared which compiles worldwide information on borosilicate waste glass corrosion. Based on the content of this document, the acceptability of canistered waste glass for geological disposal is addressed.

Waste glass corrosion in a geologic repository may be due to groundwater and/or water vapor contact. The important processes that determine the glass corrosion kinetics under these conditions are discussed. Testing data together with understanding of the long-term corrosion kinetics are used to estimate radionuclide release rates. These rates are discussed in terms of regulatory performance standards.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 333: Symposium V – Scientific Basis for Nuclear Waste Management XVII , 1993 , 3
Copyright
Copyright © Materials Research Society 1994

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