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Din avgränsning ger 42 träffar.

• 2011:05 Overview and Evaluation of the NESC Projects for Fracture Assessments of Nuclear Components

  The Network for Evaluation of Structural Components (NESC) was started in 1993 and since then six different projects have been carried out. A seventh NESC-project is still in progress. The overall objective of these projects has been to study the reliability of the entire process of structural integrity assessment within an international framework. The network is coordinated by the European...

  Innehållstyp: Publikationer

• 2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components

  During the recent years fatigue analysis procedures for nuclear components have been investigated. The most common method so far has been the American code ASME III. The basis for the current design procedures in ASME III is quite old and has now been evaluated against modern data leading to the proposal of modified design curves. Also the effect of the environment has been the subject of...

  Innehållstyp: Publikationer

• 2010:36 Guidance for the Definition and Application of Probabilistic Safety Criteria

  Safety goals are defined in different ways in different countries and also used differently. Many countries are presently developing them in connection to the transfer to risk-informed regulation of both operating nuclear power plants (NPP) and new designs. However, it is far from self-evident how probabilistic safety criteria should be defined and used. On one hand, experience indicates that...

  Innehållstyp: Publikationer

• 2011:02 The Back-End of the Nuclear Fuel Cycle in Sweden, Considerations for safeguards and data handling

  The report is a compilation report consisting of three papers. A safeguards approach for the planned encapsulation facility and the operating final repository is presented in paper 1. Special considerations concerning safeguards for the final disposal process have been discussed and incorporated into the approach. Paper 2 defines the spent fuel data that must be secured, for safeguards...

  Innehållstyp: Publikationer

• Årsredovisning 2010

  SSM Svenska...

  Innehållstyp: Publikationer

• 2011:15 Beräkning av merkostnader 2011 för rivning av de svenska kärnkraftverken och omhändertagande av restprodukter

  Denna rapport beskriver SSM:s beräkningar av framtida merkostnader inför avgiftsförslaget för 2012-2014. Beräkningen görs i enlighet med finansieringslagen och avser samtliga merkostnader fram till dess att restprodukterna från de svenska kärnkraftverken är slutligt förvarade. Enligt nuvarande beräkningar antas detta ske 2069. Uppskattningen...

  Innehållstyp: Publikationer

• 2011:12 Analysis of Barrier Performance: Modelling of Copper corrosion scenarios with and without buffer erosion

  The purpose of this project was to develop a numerical modelling capacity to address the corrosion of the copper canister under gradually changing transport conditions caused by buffer erosion and removal of buffer mass. Due to the complexity of this task, such a model cannot be realistic in all respects, but the present effort should address the feasibility of solving numerical and...

  Innehållstyp: Publikationer

• 2011:10 Strålsäkerhetsmyndighetens granskning och utvärdering av SKB:s redovisning av Fud-program 2010

  Enligt förordningen (1984:14) om kärnteknisk verksamhet (kärnteknikförordningen) ska Strålsäkerhetsmyndigheten (SSM) granska och utvärdera det program för forskning, utveckling och demonstration med mera (Fud-program) som reaktorinnehavarna enligt lagen (1984:3) om kärnteknisk verksamhet (kärntekniklagen) ska upprätta. Svensk Kärnbränslehantering...

  Innehållstyp: Publikationer

• 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

• 2011:32 The Euratom Treaty v. Treaties of the European Union: limits of competence and interaction

  Generally regulation under the Euratom Treaty could be divided into two main groups: areas explicitly regulated by the Euratom Treaty (promotion of research and dissemination of knowledge; health and safety; encouragement of investment; supplies; safeguards; the nuclear common market) and areas which are in the competence of the Euratom Community, but are not laid out in the Euratom Treaty (...

  Innehållstyp: Publikationer