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Mr Sebastien CAES (SCK-CEN)02/11/2017, 13:30National and international collaborative waste management programsOral PresentationThe Supercontainer (SC) is the reference concept for the post-conditioning of vitrified high-level nuclear waste and spent fuel in Belgium. It comprises a prefabricated concrete buffer that completely surrounds a carbon steel overpack. Welding is being considered as a final closure technique of the carbon steel overpack in order to ensure its water tightness. Welding is known to induce...Go to contribution page
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Ms Rita Vasconcelos (University of Sheffield)02/11/2017, 14:00National and international collaborative waste management programsOral PresentationIn the UK, the volume of intermediate level waste (ILW) requiring final disposal in a geological disposal facility, is almost 450,000 m3. In one of the UK conceptual scenarios for the geological disposal facility in a high-strength crystalline rock, the vaults will be backfilled with a cement-based material, known as Nirex Reference Vault Backfill (NRVB). This material will provide a physical...Go to contribution page
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Mr Ville Nenonen (University of Helsinki)02/11/2017, 14:15National and international collaborative waste management programsOral PresentationFault zones influence the mechanical properties and seismological behaviour of the Earth’s crust and also the migration and trapping of sub-surface fluids. In addition to natural processes, their behaviour has broad implications to issues such as oil and gas production, the sequestration of carbon dioxide and the geological disposal of radioactive wastes. Recent investigations carried out at...Go to contribution page
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Dr Janaka J. Kumara (Department of Civil Engineering, Meijo University, Japan)02/11/2017, 14:30National and international collaborative waste management programsOral PresentationDeep geological repositories have been proposed as a safe waste management system for high-level radioactive wastes. Sand-bentonite buffer materials are used in engineered barrier system of deep geological facilities thank to their excellent swelling properties. In this research, volumetric and strength behaviour of sand-bentonite buffer material under high confining pressures of 1-3MPa were...Go to contribution page
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Prof. Kazuya Idemitsu (Kyushu university)02/11/2017, 15:15National and international collaborative waste management programsOral PresentationThe apparent diffusion coefficients of La, Nd, Eu, Dy, Er and Lu in compacted bentonites were investigated in various bicarbonate concentration. The apparent diffusion coefficients of lanthanides tended to decrease with increase of dry density. In the lower bicarbonate conditions than 0.25 M lanthanum had the largest diffusion coefficient of ca. 10-13 m2/s at 1.0...Go to contribution page
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Dr Ryo Nakabayashi (Central Research Institute of Electric Power Industry)02/11/2017, 15:30National and international collaborative waste management programsOral PresentationThe chemical form of carbon-14 released from irradiated stainless steel is a key parameter in the safety assessment of the sub-surface disposal system in Japan. In this study, unirradiated 304 and 316 stainless-steel powders were immersed in HCl solution and in NaOH solution under a low-oxygen condition to identify the chemical form of the released carbon. The main chemical forms of the carbon...Go to contribution page
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Dr Paul Degnan (Catalystra)02/11/2017, 15:45National and international collaborative waste management programsOral PresentationThe disposal of intermediate- and high-level radioactive waste requires emplacement in suitably engineered underground facilities in order to ensure an adequate level of isolation and containment for safety and security. We now have several examples of radioactive waste management organisations who have designed and undertaken extensive multi-disciplinary site investigation projects to...Go to contribution page
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