Chemical corrosion of highly radioactive borosilicate nuclear waste glass under simulated repository conditions
Source abstract
Abstract
This review summarizes the results of the joint Japanese (Central Research Institute of Electric Power Industry, CRIEPI, Tokyo), Swiss (National Cooperative for the Storage of Radioactive Waste, NAGRA, Baden), Swedish (Swedish Nuclear Fuel and Waste Management Company, SKB, Stockholm) international ‘JSS’ project on the determination of the chemical durability of the French nuclear waste borosilicate glass, which was completed in 1988. Radioactive and nonradioactive glass specimens were investigated. A data base was created with results from glass corrosion tests performed with different water compositions, pH values, temperatures, sample surface areas (S), solution volumes (V), and flow rates. Glass corrosion tests were performed with and without bentonite and/or steel corrosion products present. Variation of the glass composition was taken into account by including the borosilicate glass ‘MW’ in the investigations, formulated by British Nuclear Fuels, plc. An understanding was achieved of the glass corrosion process in general, and of the performance of the French glass under various potential disposal conditions in particular. A special effort was made to establish a corrosion data base, using highS/Vratios in the experiments in order to understand the glass durability in the long term.
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Research context
OpenAlex topics: Nuclear materials and radiation effects · Concrete and Cement Materials Research · Glass properties and applications
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (36)
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