Abstract
Vitrified waste, overpack and buffer material are under research and development as engineered barriers in the deep geological disposal system of high-level radioactive waste. Static leach tests were carried out to understand the leaching behavior of fission products and actinides from fully radioactive vitrified waste. Carbon steel and titanium which have been evaluated as candidate overpack material were studied on the corrosion behavior. Full-scale overpacks of forged carbon steel and porcelain were fabricated, and the welding of the lid was pointed out as the most important fabrication technology to be considered. Screening of commercially available bentonite in Japan was carried out, and fundamental properties were measured. The apparent diffusivities of cesium and tritium were determined in compacted sodium bentonite with various dry densities. Volcanic glass, smectite-illite deposit, old concrete and old steel pipes were studied as 'Natural Analogue' to estimate the long term stability of engineered barrier materials.
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