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all geography including DSDP/ODP Sites and Legs
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Forsmark nuclear 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.
Deep Geologic Repositories
Crystalline Rock as a Repository for Swedish Spent Nuclear Fuel
The Russian Strategy of using Crystalline Rock as a Repository for Nuclear Waste
Selecting a Site for a Radioactive Waste Repository: A Historical Analysis
Spent Nuclear Fuel
Influence of sample preparation on MX-80 bentonite microstructure
Comparison of microstructural features of three compacted and water-saturated swelling clays: MX-80 bentonite and Na- and Ca-purified bentonite
THE USE OF CLAY AS AN ENGINEERED BARRIER IN RADIOACTIVE-WASTE MANAGEMENT – A REVIEW
Assessing the performance of a radioactive waste repository over geological timescales: past experience and the way forward
Application of a Hybrid Modeling Method for Generating Synthetic Ground Motions in Fennoscandia, Northern Europe
Methodology for studying the composition of non-interlamellar pore water in compacted bentonite
Planning of urban underground infrastructure using a broadband seismic landstreamer — Tomography results and uncertainty quantifications from a case study in southwestern Sweden
40 Ar– 39 Ar biotite and hornblende geochronology from the Oskarshamn area, SE Sweden: discerning multiple Proterozoic tectonothermal events
Interaction of titanium with smectite within the scope of a spent fuel repository: A spectroscopic approach
Appraisal of waveform repeatability for crosshole and hole-to-tunnel seismic monitoring of radioactive waste repositories
Modelling Ra-bearing baryte nucleation/precipitation kinetics at the pore scale: application to radioactive waste disposal
Abstract For the safe disposal of nuclear waste, the ability to predict the changes in oxidation states of redox active actinide elements and fission products, such as U, Pu, Tc and Np is a key factor in determining their long term mobility. Both in the Geological Disposal Facility (GDF) near-field and in the far-field subsurface environment, the oxidation states of radionuclides are closely tied to changes in the redox condition of other elements such as iron. Iron pervades all aspects of the waste-package environment, from the steel in the waste containers, through corrosion products, to the iron minerals present in the host rock. Over the long period required for nuclear waste disposal, the chemical conditions of the subsurface waste package will vary along the entire continuum from oxidizing to reducing conditions. This variability leads to the expectation that redox-active components such as Fe oxides can undergo phase transformations or dissolution; to understand and quantify such a system with respect to potential impacts on waste package integrity and radionuclide fate is clearly a serious challenge. Traditional GDF performance assessment models currently rely upon surface adsorption or single-phase solubility experiments and do not deal with the incorporation of radionuclides into specific crystallographic sites within the evolving Fe phases. In this chapter, we focus on the iron-bearing phases that are likely to be present in both the near and far-field of a GDF, examining their potential for redox activity and interaction with radionuclides. To support this, thermodynamic and molecular modelling is particularly important in predicting radionuclide behaviour in the presence of Fe-phases. Examination of radionuclide contamination of the natural environment provides further evidence of the importance of Fe-phases in far-field processes; these can be augmented by experimental and analogue studies.