Title

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

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.

Meeting Name

16th International Symposium on the Scientific Basis for Nuclear Waste Management (1992: Nov. 30-Dec. 4, Boston, MA)

Department(s)

Geosciences and Geological and Petroleum Engineering

Keywords and Phrases

Chemical Reactions; Corrosion; Geological Repositories; Radioactive Waste Encapsulation; Radioactive Waste Vitrification; High Level Nuclear Waste; Long Term Predictions; Mechanistic Modelling; Waste Glass Alterations; Borosilicate Glass

International Standard Book Number (ISBN)

1558991891

International Standard Serial Number (ISSN)

2729172

Document Type

Article - Conference proceedings

Document Version

Citation

File Type

text

Language(s)

English

Rights

© 1993 Materials Research Society (MRS), All rights reserved.

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