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  • 2008:10 International Expert Review of SR-Can: Engineered Barrier Issues

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has recently submitted a license application for the construction of a spent fuel encapsulation plant. SKB plans to submit a further license application in 2009 for the construction of a repository for the disposal spent nuclear fuel. In connection with the first of these applications, SKB published a safety report, known as SR-Can,...

    Innehållstyp: Publikationer
  • 2007:32 Low pH Cements

    Concrete and cement are used in constructions as well as in conditioning of waste in repositories for radioactive waste. The development of low pH cements for use in geological repositories for radioactive waste stem from concerns over the potential for deleterious effects upon the host rock and other EBS materials (notably bentonite) under the hyperalkaline conditions (pH > 12) of cement...

    Innehållstyp: Publikationer
  • 2007:29 Intercomparison of Cement Solid-Solution Models

    Many concepts for the geological storage of radioactive waste incorporate cement based materials, which act to provide a chemical barrier, impede groundwater flow or provide structural integrity of the underground structures. Thus, it is important to understand the long-term behaviour of these materials when modelling scenarios for the potential release and migration of radionuclides. In the...

    Innehållstyp: Publikationer
  • 2007:07 DECOVALEX-THMC Project - Task A

    This report presents the definition of the first phase, Task A-1, of the Task A of the international DECOVALEX project. The task is a working example of how interaction between THMC modelling and SA analysis could be performed. Starting with the technical definition of the Task A, the report presents the results of preliminary THM calculations with a purpose of an initial appreciation of the...

    Innehållstyp: Publikationer
  • 2007:21 On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden

    The aim of this applied study has been to demonstrate how a cost calculation is done in a systematic way. The framework of the project has been limited to older nuclear installations in Sweden. Furthermore, it may be envisaged that the process of making regular estimates of all the parameters is crucial in preparatory phases of decommissioning and dismantling processes. A secondary aim of the...

    Innehållstyp: Publikationer
  • 2007:03 Variability and Uncertainties of Key Hydrochemical Parameters for SKB Sites

    An important part of the site investigations conducted by the Swedish Nuclear Fuel and Waste Management Company (SKB) is the characterisation of groundwater chemical conditions in the deep bedrock environment where a final repository for spent nuclear fuel is planned to be located. This work is currently in its final stages at the two candidate sites, Forsmark and Laxemar, and should be...

    Innehållstyp: Publikationer
  • 2007:02 Stakeholder involvement in Swedish nuclear waste management

    This report have attempted to show the development of stakeholder involvement in the siting of a final repository for Sweden’s spent nuclear fuel as resembling something other than a straightforward linear process of improvement and refinement. Stakeholder involvement has developed, over the past 15 years or so, in something more like a patchwork of different shapes and forms. Some of the...

    Innehållstyp: Publikationer
  • 2015:28 Utvärdering av materialdata för befintliga betongkonstruktioner - med inriktning på verifiering av förankringar vid kärntekniska anläggningar

    Bakgrund I de Svenska kärnkraftverken finns ett stort antal fästplattor som är ingjutna alternativt eftermonterade. Fästplattan består av en förankringsplatta med tillhörande betonginfästning. Kapaciteten för flera av de viktigare brottmoderna för betonginfästningar styrs av hållfastheten hos omgivande betong. Betongens hållfasthet...

    Innehållstyp: Publikationer
  • 2015:37 Models for axial relocation of fragmented and pulverized fuel pellets in distending fuel rods and its effects on fuel rod heat load

    Haverifall med kylmedelsförlust (LOCA) i lättvattenreaktorer kan leda till överhettning av bränslestavar, utvidgning av stavarnas kapslingsrör, samt axiell omflyttning av bränslekutsfragment i de delar av stavarna som expanderat. Bränsleomflyttningen kan koncentrera värmebelastningen till en begränsad del av stavarna och därigenom öka risken...

    Innehållstyp: Publikationer
  • 2015:24 Dimensionering av nukleära byggnadskonstruktioner (DNB)

    Strålsäkerhetsmyndigheten (SSM) och de svenska tillståndshavarna har tidigare i ett samfinansierat forskningsprojekt tagit fram anvisningar för dimensionering av nukleära byggnadskonstruktioner, DNB. Rapporten som är baserad på Eurokoderna publicerades som SSM rapport 2014:06 För att ytterligare förbättra DNB och för att säkerställa...

    Innehållstyp: Publikationer