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Oskarshamn power plant
Geological disposal of radioactive waste—Experience from operating facilities in Sweden
Abstract Geological disposal has been the basis for the Swedish program for disposal of radioactive waste since its beginning in the mid-1970s. Two underground facilities have been in operation since the late 1980s. The construction of the final repository for short-lived, low- and intermediate-level waste, SFR (Swedish final repository for radioactive operational waste), started in 1983, and it was put into operation in 1988. The facility is located 50 m below the sea, close to the Forsmark nuclear power plant, where the sea has a depth of ∼5 m. Low-level waste is placed in four rock vaults, each of which has a length of 160 m. Intermediate-level waste is stored in a concrete silo that has a height of 50 m and an inner diameter of 26 m. The disposal vaults are connected to the surface by two parallel access tunnels. The total disposal capacity is 63,000 m 3 , of which about one-half is currently in use. An expansion of the SFR is planned to accommodate radioactive waste from the decommissioning of the nation's power plants. Construction of the interim storage facility for spent nuclear fuel, Clab, started in 1980, and the facility was put into operation in 1985. The facility is located at the Oskarshamn nuclear power plant. The fuel assemblies are stored in water pools located in two 120-m-long rock chambers. The roof of the rock chambers is ∼30 m below the ground surface. Construction of a second storage vault has recently been completed. The Äspö Hard Rock Laboratory is an underground facility for developing and testing characterization methods and the different components of a system for deep geological disposal under realistic repository conditions. The facility reaches a depth of 460 m below the surface. After 5 yr of construction, it was put into operation in 1995. The licensing, construction, and operation of these facilities have provided valuable experience that is being used for the site characterization and design work currently in progress for the deep geological repository for spent nuclear fuel. The spent nuclear fuel will be disposed of in a repository located at depths between 400 and 700 m. The disposal concept is based on isolation of the spent fuel in copper canisters surrounded by a buffer of highly compacted bentonite placed in a borehole in granitic rock. Site investigations are currently in progress at two potential sites. This project is a major geoscientific undertaking that is planned to be completed in 2009 with the selection of one of the sites for the deep repository.
40 Ar– 39 Ar biotite and hornblende geochronology from the Oskarshamn area, SE Sweden: discerning multiple Proterozoic tectonothermal events
Deep Geologic Repositories
Selecting a Site for a Radioactive Waste Repository: A Historical Analysis
Overview of less advanced programmes and their requirements
Phosphates and Nuclear Waste Storage
Crystalline Rock as a Repository for Swedish Spent Nuclear Fuel
OH defects in quartz as monitor for igneous, metamorphic, and sedimentary processes
COMBINED SALT AND TEMPERATURE IMPACT ON MONTMORILLONITE HYDRATION
Abstract This paper describes how four scientific and safety relevant issues have been addressed in special-purpose research laboratories focusing on the geological disposal of high level and long-lived radioactive waste. These are: (a) the effects of heat on the engineered barriers and the geological environment; (b) the geochemical characterization of pore-water in argillaceous rocks; (c) the diffusion and retention of radionuclides; and (d) the full-size sealing of a waste emplacement. They are illustrated by experiments conducted in five underground research laboratories (URLs), three of which are in clay formations (Mol in Belgium, Centre de Meuse–Haute-Marne in France, and Mont Terri Rock Laboratory in Switzerland) and two in granite (Aspö Hard Rock Laboratory in Sweden and Grimsel Test Site in Switzerland). This paper highlights how the various types of experiments are related and how their results have been applied to foster progress. The most complex experiments have revealed artefacts and technical or methodological difficulties associated with interactions among multiple phenomena, the occurrence or intensity of which cannot be analysed by simple models. In turn, these difficulties have prompted experiments targeted at elementary phenomena, thereby encouraging the development of new investigation protocols and monitoring tools. More than 30 years of investigations in special-purpose URLs show the benefits of in-situ experimental programmes in the context of radioactive waste management. The laboratories have opened up avenues for research and advanced knowledge and technology. Thanks to a large component of international cooperation, they have made it possible to mobilize the financial and human resources required for this type of research. They have, above all, shared thoughts and promoted interdisciplinary studies around the same subject. They make common strategies possible at international level.