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Din avgränsning ger 299 träffar.

• 2017:08 Konsekvenser av instruktioners utformning och användning

  Bakgrund Inom säkerhetskritiska branscher används ofta ett instruktionsstyrt arbetssätt i hög utsträckning. Miljön i sig och de eventuella risker som kan finnas inom verksamheten man befinner sig i kan leda till att man vill föreskriva exakt hur och när arbete ska genomföras. Detta anses skapa bland annat trygghet, förutsägbarhet och stabilitet.

  Innehållstyp: Publikationer

• 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...

  Innehållstyp: Publikationer

• 2018:11 Bedömning av spännkraftförluster genom deformationsmätning av reaktorinneslutningen vid uppstart – DEFORM

  Bakgrund Den strukturella integriteten av reaktorinneslutningen är beroende av spännarmeringens spännkraft. Spännkraften minskar med tiden genom bl.a. omlagring till själva betongen. I byggnormen finns standardformler som beaktar dessa förluster men lite kunskap finns gällande hur inneslutningens unika geometri och miljö har för inverkan på spännkraftsförlusterna.

  Innehållstyp: Publikationer

• 2009:30 A Review of Evidence for Corrosion of Copper by water

  The planned spent nuclear fuel repository in Sweden relies on a copper cast iron canister as the primary engineered barrier. The corrosion behaviour of copper in the expected environment needs to be thoroughly understood as a basis for the post-closure safety analysis. It has been shown that corrosion may indeed be the primary canister degradation process during the utilised assessment period...

  Innehållstyp: Publikationer

• 2007:17 Spent Fuel Dissolution and Source Term Modelling in Safety Assessment

  SKI is preparing to review the license applications being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB) for a final repository for the geological disposal of spent nuclear fuel (SFL-2) in the year 2009. As part of its preparation, SKI is conducting a series of technical workshops on key aspects of the Engineered Barrier System (EBS) and spent fuel. This workshop...

  Innehållstyp: Publikationer

• 2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code

  The aim of this applied study has been to describe in a systematic way an appropriate methodological sequence for cost estimation of crucial parameters in decontamination and decommission processes. The work has been limited to older nuclear installations and facilities. Furthermore, it may be envisaged that the process of estimating the parameters of decommissioning is one of the main issues...

  Innehållstyp: Publikationer

• 2009:22 Alternative modelling of brittle structures in a sub-area of the SKB candidate area at Forsmark, eastern Sweden

  A reasonable understanding of the character of the bedrock hosting a deep geological repository, i.e. the natural barrier, is an important component in the safety assessment of the deep geological repository for spent nuclear fuel. The structures in the rock, together with the regional stress field, affect the mechanical stability of the bedrock and the ground water transport within the...

  Innehållstyp: Publikationer

• 2010:23 On Decommissioning Costs of the Ranstad Site

  A demanding task for the present generation is to assure that appropriate financial resources are injected into the Swedish Nuclear Waste Fund. It will thereby be possible for coming generations to undertake efficient measures in the decommissioning and dismantling of older nuclear facilities. To undertake such measures in the context of Swedish as well as European environmental and health...

  Innehållstyp: Publikationer

• 2016:31 Measures and method characteristics for early evaluation of safe operation in nuclear power plant control room systems

  The Swedish Radiation Safety Authority’s (SSM) experience is that there is a need to develop evaluation methods in parallel with the development of control rooms in conjunction with construction modifications and other changes. This includes more indepth analysis of the methods used today. Another aspect is that conventional methods of evaluating control rooms and issues need to be...

  Innehållstyp: Publikationer

• 2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA

  Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to evaluate the PRO-LOCA code. It is a computer code, developed by Battelle in the USA, in which the leak- and rupture probabilities of piping in nuclear power plants are analysed. The pipe systems may contain the damage mechanisms fatigue and/or...

  Innehållstyp: Publikationer