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  • 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...

    Content type: Publications
  • 2007:08 DECOVALEX-THMC - Task B

    This report summarizes the work contributed to Phase 2 of Task B of the international DECOVALEX-THMC project, which took place during the period of March 2004 to May 2006. The Phase 2 work incorporated the use of a wide range of numerical models to simulate the failure of a number of intact rock core samples, from the APSE tunnel at Äspö HRL, as tested in uniaxial compression and other...

    Content type: Publications
  • 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...

    Content type: Publications
  • 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...

    Content type: Publications
  • 2011:26 The influence of temperature and fluid pressure on the fracture network evolution around deposition holes of a KBS-3V concept at Forsmark, Sweden

    In preparation for the review of SKB’s license application for disposal of spent nuclear fuel, SSM is conducting studies to evaluate the performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at about 500 m depth and embedded in clay. Thus, the rock, the clay and the copper canister...

    Content type: Publications
  • 2012:11 Issues in the corrosion of copper in a Swedish high level nuclear waste repository

    The objective with this research project was to increase knowledge in the area of copper corrosion in the planned repository environment and obtain information on how copper corrosion evolves during the assessment period of 100 000 years. The equilibrium chemical composition of groundwater close to the canister as a function of temperature has been calculated by use of a thermodynamics code...

    Content type: Publications
  • 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...

    Content type: Publications
  • 2019:23 Participation in the European Committee for Standardization's workshop regarding civil structures

    SSM perspective Background During the period 2014-2018, a CEN1 workshop (Phase 2 Prospective Group 3 civil works) have been carried out. The aim of the workshop is to provide a base founded on the French standard in order to be able to establish a possible future European standard for the design of civil structures at nuclear power plants. The workshop has identied which additional...

    Content type: Publications
  • 2019:20 Assessment of structures subject to concrete pathologies (ASCET), phase 3

    SSM perspective Background ASCET is an international research project initiated by WGIAGE1 OECD2 / NEA3. WGIAGE Concrete subgroup is a working group within the OECD / NEA whose task is to address issues concerning the maintenance of the integrity of concrete structures, proposals for general principles to optimally handle the challenges of integrity, especially with regard to ageing of...

    Content type: Publications
  • 2019:03 Evaluation of the hydrodynamic model in PARET/ANL

    Background The fuel rod analysis program SCANAIR has been developed by IRSN (Institut de Radioprotection et de Sûreté Nucléaire) for analysis of reactivity initiated accidents (RIA) in light water reactors. The Swedish Radiation Safety Authority (SSM) has access to SCANAIR in exchange for annual contributions for its further development. This ensures a possibility for SSM to do...

    Content type: Publications