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2007:11 Review of Quality Assurance in SKBs Repository Research Experiments
SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. As a preparation for SR-Site SKB has recently produced the SRCan safety assessment, which is currently in review. The assessment of long-term safety is based on a broad range of...
Innehållstyp: Publikationer -
2009:21 The geological history of the Baltic Sea a review of the literature and investigation tools
The bedrock in Sweden mainly comprises Proterozoic magmatic and metamorphic rocks older than a billion or one and a half billion years with few easily distinguished testimonies for the younger history. For construction of a geological repository for deposition of nuclear waste it is important to understand the late, brittle, geological events to be able to estimate its influence and...
Innehållstyp: Publikationer -
2008:47 Selected Models for Key Processes in a Nuclear Waste Repository
The conceptual design of the disposal of spent nuclear fuel in Sweden is based on a multibarrier system. In the KBS-3 concept, the bentonite buffer is a barrier with the primary purpose of surrounding and protecting the canister. The bentonite buffer is expected to prevent or minimise the water exchange with the surrounding rock and protect the canister against mechanical damages caused by...
Innehållstyp: Publikationer -
2009:08 Shear-induced Fracture Slip and Permeability Change - Implications for Long-term Performance of a Deep Geological Repository
Opening of fractures induced by shear dilation or normal deformation can be a significant source of fracture permeability change in jointed rock, which is important for the performance assessment of geological repositories for spent nuclear fuel. As the repository generates heat and later cools the fluid-carrying ability of the rocks becomes a dynamic variable during the lifespan of the...
Innehållstyp: Publikationer -
2007:30 Modelling the Interaction of Low pH Cements and Bentonite
Concrete and cement are used in constructions as well as in conditioning of waste inrepositories for radioactive waste. It is well known that in the hyperalkaline conditions (pH > 12) of standard cement pore fluids, there is potential for deleterious effects upon the host rock and other EBS materials, notably bentonite, in geological repositories. Low pH cements are beginning to be considered...
Innehållstyp: Publikationer -
2006:36 Mechanical Integrity of Canisters Using a Fracture Mechanics Approach
This report presents the methods and results of a research project for Swedish Nuclear Power Inspectorate (SKI) about numerical modeling of mechanical integrity of cast-iron canisters for the final disposal of spent nuclear fuel in Sweden, using combined boundary element (BEM) and finite element (FEM) methods The objectives of the project are: 1) to investigate the possibility of initiation...
Innehållstyp: Publikationer -
2007:17 Spent Fuel Dissolution and Source Term Modelling in Safety Assessment
SKI is preparing to review the license applications being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB) for a final repository for the geological disposal of spent nuclear fuel (SFL-2) in the year 2009. As part of its preparation, SKI is conducting a series of technical workshops on key aspects of the Engineered Barrier System (EBS) and spent fuel. This workshop...
Innehållstyp: Publikationer -
2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister
The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration...
Innehållstyp: Publikationer -
2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code
The aim of this applied study has been to describe in a systematic way an appropriate methodological sequence for cost estimation of crucial parameters in decontamination and decommission processes. The work has been limited to older nuclear installations and facilities. Furthermore, it may be envisaged that the process of estimating the parameters of decommissioning is one of the main issues...
Innehållstyp: Publikationer -
2005:27 DECOVALEX III/BENCHPAR PROJECTS Approaches to Upscaling Thermal-Hydro- Mechanical Processes in a Fractured Rock Mass and its Significance for Large-Scale Repository Performance Assessment
Summary of Findings Report of BMT2/WP3...
Innehållstyp: Publikationer