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Din avgränsning ger 268 träffar.

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  • 2012:63 Technical Note, Review of Radionuclide Sorption on Bentonite and Forsmark Bedrock Material

    Denna rapport granskar sorption-data för bentonit och berg vilka har använts i säkerhetsanalysen SR-Site. Det kan konstateras att härledningen av Kd-värden har gjorts på ett systematiskt sätt och att presentationen av resultat är uttömmande. Kontroller visar att härledning och överföring av resultat kan betraktas som spårbar. Det...

    Innehållstyp: Publikationer
  • 2012:58 Technical Note, Independent radionuclide transport modelling – Reproducing results for main scenarios

    As part of the initial technical review of SR-Site, we applied a simplified model to approximate Swedish Nuclear Fuel and Waste Management Company (SKB) computations related to the transport of radionuclides at the planned KBS–3 repository at the Forsmark site in Sweden. The objective was to provide insights and recommendations to the Swedish Radiation Safety Authority (SSM) on potential...

    Innehållstyp: Publikationer
  • 2012:60 Technical Note, Handling of climate related issues in the safety assessment SR-Site

    The application is based on research carried out over several decades and is an impressive compilation of data and knowledge of the site of Forsmark. The sections on climate, glaciations and permafrost have developed continuously through the earlier compilations reported (e.g. the SR-97-reports). Much has been improved over the years while new question marks have occurred and some known...

    Innehållstyp: Publikationer
  • 2012:55 Technical Note, Review of SKB’s Radionuclide Transport Methodology

    As part of SSM’s Initial Review Phase of SKB’s SR-Site safety assessment of the final disposal of spent nuclear fuel at the Forsmark site, Quintessa has been requested by SSM to consider whether SKB’s methodology to abstract FEPs (features, events, processes), as well as site information and other data, into assessment models for radionuclide transport is appropriate and sufficient for its...

    Innehållstyp: Publikationer
  • 2012:62 Technical Note, Review of the MARFA Code

    As part of SSM’s Initial Review Phase of SKB’s SR-Site safety assessment of the final disposal of spent nuclear fuel at the Forsmark site, Quintessa has been requested by SSM to review SKB’s MARFA code and consider whether the technical arguments and assumptions used for developing the code are sound, appropriate and adequate to support its use in SR-Site. This Technical Note summarises the...

    Innehållstyp: Publikationer
  • 2012:18 Technical Note, SR-Site Independent Modelling of Engineered Barrier Evolution and Coupled THMC: Contribution to the Initial Review Phase

    This review has focussed mainly on the modelling of the Engineered Barrier System (EBS) evolution, which includes coupled thermal, hydraulic, mechanical and chemical (THMC) processes. Additionally, the role of the EBS in the wider safety case was reviewed, including its treatment in scenarios and its representation in conceptual models since this provided the motivation for the modelling work...

    Innehållstyp: Publikationer
  • 2012:33 Technical Note, Review of Groundwater Chemistry in SKB’s Safety Assessment SR-Site

    This initial review examined SKB’s characterization of groundwater chemistry at the Forsmark site and its evolution during long time periods under different possible climates in the future. The review considered whether the geochemical data provided by SKB are reasonable and sufficient and whether the methods used by SKB for projecting geochemical conditions into the future are appropriate.

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • 2012:34 Technical Note, Review of FEP Handling in the SR-Site Safety Assessment: Initial Review Phase

    On 16th March 2011 the Swedish Nuclear Fuel and Waste Management Company, SKB, submitted applications for licences to construct a spent nuclear fuel encapsulation facility in Oskarshamn and a repository for final disposal of the encapsulated fuel in Forsmark. SKB’s applications are currently being reviewed by the Swedish Radiation Safety Authority, SSM, and the Land and Environmental Court in...

    Innehållstyp: Publikationer
  • 2012:08 Deterministic Assessment of Future Costs for Dismantling (FA)

    In this study a model for advanced deterministic cost calculation has been used to find a parametric value on the cost for dismantling of the FA-facility. The study gives good description of good practise to collect, test and utilise input data in a systematic way in order to make prudent cost estimates for any particular nuclear installation The Swedish Law stipulates that future expenses...

    Innehållstyp: Publikationer