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High-Level Nuclear-Waste Borosilicate Glass: A Compendium of Characteristics

Published online by Cambridge University Press:  01 January 1992

J. C. Cunnane
Affiliation:
Argonne National Laboratory, Argonne, IL 60439-4837
J. K. Bates
Affiliation:
Argonne National Laboratory, Argonne, IL 60439-4837
W. L. Ebert
Affiliation:
Argonne National Laboratory, Argonne, IL 60439-4837
X. Feng
Affiliation:
Argonne National Laboratory, Argonne, IL 60439-4837
J. J. Mazer
Affiliation:
Argonne National Laboratory, Argonne, IL 60439-4837
D. J. Wronkiewicz
Affiliation:
Argonne National Laboratory, Argonne, IL 60439-4837
J. Sproull
Affiliation:
Westinghouse Savannah River Company, Aiken, SC 29808
W. L. Bourcier
Affiliation:
Lawrence Livermore National Laboratory, Livermore, CA 94550
B. P. Mcgrail
Affiliation:
Battelle Pacific Northwest Laboratory, Richland, WA 99352
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Abstract

With the imminent startup, in the United States, of facilities for vitrification of high-level nuclear waste, a document has been prepared that compiles the scientific basis for understanding the alteration of the waste glass products under the range of service conditions to which they may be exposed during storage, transportation, and eventual geologic disposal. A summary of selected parts of the content of this document is provided.

Waste glass alterations in a geologic repository may include corrosion of the glass network due to groundwater and/or water vapor contact. Experimental testing results are described and interpreted in terms of the underlying chemical reactions and physical processes involved. The status of mechanistic modeling, which can be used for long-term predictions, is described and the remaining uncertainties associated with long-term simulations are summarized.

Type
Research Article
Copyright
Copyright © Materials Research Society 1993

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References

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