High-Level Nuclear-Waste Borosilicate Glass: A Compendium of Characteristics
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HIGH-LEVEL NUCLEAR-WASTE BOROSILICATE GLASS: A COMPENDIUM OF CHARACTERISTICS J. C. Cunnane, I J. K. Bates, 1 W. L. Ebert, 1 X. Feng,1 J. J. Mazer, 1 D. J. Wronkiewicz, 1 4 3 2 J. Sproull, W. L. Bourcier, and B. P. McGrail 1 Argonne 2
National Laboratory, Argonne, IL 60439-4837. Westinghouse Savannah River Company, Aiken, SC 29808. Lawrence Livermore National Laboratory, Livermore, CA 94550. 4 Battelle Pacific Northwest Laboratory, Richland, WA 99352. 3
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. INTRODUCTION AND BACKGROUND Current plans call for startup of facilities for vitrification of high-level nuclear waste, stored in tanks at Savannah River, South Carolina, and West Valley, New York, within the next few years. The products from these facilities will be canistered high-level nuclear waste borosilicate glass. These products will be stored, transported, and eventually disposed of in a geologic repository. The behavior of the glass, under the range of service conditions that tit is likely to experience, is a subject of considerable scientific and public interest. Fortunately, an enormous body of pertinent scientific information has been generated,
worldwide, over the past few decades, regarding this subject. The document entitled "HighLevel Nuclear Waste Borosilicate Glass: A Compendium of Characteristics" has been prepared to consolidate this information. The intent of this ambitious undertaking is to support resolution of issues concerning waste glass degradation that may arise during startup of the vitrification facilities. The history of the development of borosilicate glass as a waste form reflects a broad international consensus on its suitability as a waste form for immobilization of high-level nuclear waste. After the initial recognition of glass as a promising medium for immobilization of high-level nuclear waste in the mid 1950's [1 ), the technology for vitrification of high-level nuclear waste has been pursued internationally for four decades. The first production facility to vitrify high-level radioactive waste began operation, at Marcoule, in France, in 1978. Borosilicate glass has now been selected as the final waste form in most countries that have h
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