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  • 2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents

    Ali R. Massih, Lars Olof Jernkvist SSM English...

    Innehållstyp: Publikationer
  • 2008:12 Independent Calculations for the SRCan Assessment

    External review contribution in support of SKI's and SSI's review of SR-Can The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear...

    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
  • 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
  • 2007:02 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
  • 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
  • 2008:57 Discrete Feature Model (DFM) User Documentation

    This manual describes the DiscreteFeature Model (DFM) software package for modelling groundwater flow and solute transport in networks of discrete features. A discretefeature conceptual model represents fractures and other waterconducting features around a repository as discrete conductors surrounded by a rock matrix which is usually treated as impermeable. This approximation may be valid for...

    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
  • 2014:31 Degradering i betong och armering med avseende på bestrålning och korrosion

    De primära egenskaperna för betongstrukturer i ett kärnkraftverk är dess strukturella styrka och möjlighet att avskärma joniserande strålning. Skade- och belastningsbilden kan komma att påverkas av genomförda och planerade effekthöjningar samt planerade driftsförlängningar av de svenska reaktorerna. Kunskap om huruvida betongen i kärnkraftverk...

    Innehållstyp: Publikationer
  • 2015:44 Krav på funktion, konstruktion och provning av reaktorinneslutningar

    Bakgrund I Sverige behöver SSM skaffa vidare kunskap inom olika områden inom nukleära byggnadskonstruktioner bl.a. reaktorinneslutningar. Syfte Syftet med projektet "Krav på funktion, konstruktion och provning av reaktorinneslutningar" är att sammanställa information för att belysa viktiga reaktorinneslutningsfrågor vid byggnation. Den sammanställda...

    Innehållstyp: Publikationer