Author:
Cunnane J. C.,Allison J. M.
Abstract
ABSTRACTFacilities 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.
Publisher
Springer Science and Business Media LLC
Reference26 articles.
1. Leach Testing of Waste Glasses Under Near-Saturation Conditions
2. 25 Title 10, Chapter 1, Code of Federal Regulations, Part 60, U.S. Nuclear Regulatory Commission (1986).
Cited by
3 articles.
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