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Din avgränsning ger 42 träffar.

• 2011:19 Experimental evaluation of influence from residual stresses on crack initiation and ductile crack growth at high primary loads

  Cracked components are usually subjected to loads causing both primary and secondary stresses, e.g. welding components. Engineering assessment approaches, such as the ASME XI code and the R6 procedure, are commonly used to conduct integrity assessment of such components. There has been an ongoing debate how to treat secondary stresses using engineering assessment methods. The nature of these...

  Innehållstyp: Publikationer

• 2011:29 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 17

  This report constitutes Stage 17 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Results up to Stage 16 were reported in SKI and SSM reports, as listed below and in the Summary. The results have also been published in international journals and have been included in both licentiate- and doctor’s degrees.

  Innehållstyp: Publikationer

• 2011:17 Structural Health Monitoring of Piping in Nuclear Power Plants – A Review of Efficiency of Existing Methods

  SSM needs to acquire knowledge about new applied Non-Destructive Engineering (NDE) techniques and their efficiency. One area that is discussed more frequently is Structural Health Monitoring (SHM). SSM needs to investigate the international experiences of SHM from the nuclear industry. SSM also wants to have more information about the capabilities and the limitations of NDE methods The first...

  Innehållstyp: Publikationer

• 2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report

  The MERIT project has been an internationally financed program with the main purpose of developing probabilistic models for piping failure of nuclear components and to include these models in a probabilistic code named PRO-LOCA. The principal objective of the project has been to develop probabilistic models for piping failure of nuclear components and to include these models in a...

  Innehållstyp: Publikationer

• 2011:18 Strålsäkerhetsläget vid de svenska kärnkraftverken 2010

  Enligt Strålsäkerhetsmyndighetens (SSM:s) regleringsbrev ska myndigheten senast den 31 maj 2011 till regeringen redovisa strålsäkerhetsläget vid de svenska kärnkraftverken. Föreliggande rapport utgör denna redovisning. 100 SSM SSM Svenska Enligt Strålsäkerhetsmyndighetens (SSM:s) regleringsbrev ska myndigheten senast den 31 maj 2011 till regeringen...

  Innehållstyp: Publikationer

• 2011:26 The influence of temperature and fluid pressure on the fracture network evolution around deposition holes of a KBS-3V concept at Forsmark, Sweden

  In preparation for the review of SKB’s license application for disposal of spent nuclear fuel, SSM is conducting studies to evaluate the performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at about 500 m depth and embedded in clay. Thus, the rock, the clay and the copper canister...

  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