Development of the Engineered Barriers for the Deep Geological Disposal of High-Level Radioactive Waste

by N. Sasaki, Power Reactor and Nuclear Fuel, Development Corp, Japan,
H. Ishikawa, Power Reactor and Nuclear Fuel, Development Corp, Japan,
K. Miyahara, Power Reactor and Nuclear Fuel, Development Corp, Japan,
K. Yamada, Power Reactor and Nuclear Fuel, Development Corp, Japan,
Y. Yusa, Power Reactor and Nuclear Fuel, Development Corp, Japan,



Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1990

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.

Subject Headings: Radioactive wastes | Waste disposal | Geology | Pipe materials | Radioactive materials | Hazardous materials | Leaching | Carbon fibers | Japan | Asia

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