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  • 2011:11 Handling Interfaces and Time-varying Properties in Radionuclide Transport Models

    Quintessa’s QPAC code has been used to investigate the Qeq approach. The conclusions from this simulation study are the following. The basic approach to calculating Qeq values is sound, however, narrow channels could lead to the same release as larger fractures with the same pore velocity, so a channel enhancement factor of √10 should be considered. A spalling zone that increases the area of...

    Innehållstyp: Publikationer
  • 2009:32 On Younger Stakeholders and Decommissioning of Nuclear Facilities

    An appropriate balance in this regard must be based on a proper understanding of the values and value functions of younger citizens. Such information must thus be an integral part of the knowledge base to be used when plans and processes are being developed for dismantling and decommissioning of nuclear power plants and other older nuclear facilities. In the present project, empirical data...

    Innehållstyp: Publikationer
  • 2009:31 A Review of the Decommissioning Costs of the Ranstad Site

    The main objective of this study has been to review the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. Analyses of some detailed comparative empirical information have been used in the context of preliminary “bench-marking” studies. The estimated costs for decommissioning of the old uranium mine in Ranstad have been...

    Innehållstyp: Publikationer
  • 2013:20 Terrestrial Biosphere Modelling of C-14 Research

    The need to address radiological impacts from 14C released to the biosphere has been recognized for some time. However, because of its role in biological processes and its ecological cycling, the standard methods employed to model long-term radionuclide transport and accumulation in the biosphere cannot be used satisfactorily for 14C. In 2011, the Swedish Radiation Safety Authority (SSM)...

    Innehållstyp: Publikationer
  • 2013:26 Degradering av berg, förstärkningar och injektering i tunnlar

    Befintliga och planerade slutförvarsanläggningar för radioaktivt avfall kräver särskilda kunskaper för dess projektering och för att följa upp dess utveckling under drift samt efter förslutning. Kunskaper behövs för att välja anläggningens utformning, passande material, underhåll samt förslutningsmetoder. De långa...

    Innehållstyp: Publikationer
  • 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
  • 2012:60 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
  • 2012:37 Technical Note, Selective review of the hydrogeological aspects of SR-Site

    This review of the hydrogeology is selective. It focuses on the measurement, interpretation and modelling of the potential repository host rock, that is the rock domain FFM01<-400m. It accepts as reasonably accurate the measurement and representation of the more transmissive parts of the hydrogeological system, particularly the near-surface 150m in the form presented by SKB. SKB have decided...

    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
  • 2014:39 Technical Note, “Wormhole” and Multiple Loss of Buffer Safety Function Scenarios

    This Technical Notes reviewed the issues that may cause canister corrosion other than the cases evaluated by SKB, which may belong to “What-if” canister corrosion scenarios. This Notes, in particular, addressed two potential canister corrosion scenarios: “wormhole” formation and loss of multiple buffer safety functions. The “wormhole” scenario was hypothesized during the SSM Workshop on...

    Innehållstyp: Publikationer