Abstract
Iron corrosion products of the steel canister in the nuclear waste container are highly silica sorptive materials and very much expected to delay formation of the protective layer (gel) on the nuclear glass interface. This study is focusing on the role of the iron carbonates (ankerite), which is probably one of iron corrosion products and already exists in the clay structure of the disposal depth. French SON68 inactive reference glass (alternative to the R7T7- type) samples are planned to leach in different series of experimental models with dissimilar quantities of natural ankerite. All batch experiments will be cultivated in synthetic Callovo-Oxfordian groundwater; where different pH (4-9) values and temperatures (35, 50, 90 °C) are considered. In this paper the state of the art of the radioactive waste glass corrosion in the circumstances of deep geological disposal were extensively studied.
Highlights
Last century, nuclear energy started taking part in energy production and research sectors
Spent fuel is reprocessed to generate new nuclear fuel used in economic reactors and the remaining fission products (129I, 90Sr, 99Tc, 79Se, 36Cl, and 135Cs) and other actinides are considered as High Level radioactive Waste (HLW)
Experiments have been performed by 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 project (JSS) on determination of the chemical durability of the French nuclear waste borosilicate glass (R7T7 type glass), which was completed in 1988
Summary
Nuclear energy started taking part in energy production and research sectors. The long life highly radioactive waste generated from the nuclear reactors is one of the critical issues regarding this. Spent fuel generated from the nuclear reactors is considered as High Level radioactive Waste (HLW). Disposal of the HLW in deep geological formation in multi-layer containers is agreed by the most involved countries and highly recommended by the International Atomic Energy Agency (IAEA). The glass matrix is formed to pellet shape and poured into stainless steel containers to facilitate its handling, storage and disposal operations. It is embedded in a buffer i.e. concrete isolation in the clay-stones [4]
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