High-Level Nuclear-Waste Borosilicate Glass: A Compendium of Characteristics
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.
J. C. Cunnane et al., "High-Level Nuclear-Waste Borosilicate Glass: A Compendium of Characteristics," Materials Research Society Symposium Proceedings, vol. 294, pp. 225-232, Materials Research Society (MRS), Jan 1993.
16th International Symposium on the Scientific Basis for Nuclear Waste Management (1992: Nov. 30-Dec. 4, Boston, MA)
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)
International Standard Serial Number (ISSN)
Article - Conference proceedings
© 1993 Materials Research Society (MRS), All rights reserved.
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