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Din avgränsning ger 87 träffar.

• 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

• 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

• 2010:35 Probabilistic Safety Goals for Nuclear Power Plants; Phases 2-4 / Final Report

  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

• 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

• 2011:33 Mathematical modelling of ultrasonic testing of components with defects close to a non-planar surface

  The report describes work that has been performed in order to model ultrasonic testing of components that contain a defect close to a non-planar surface. The studies have been performed in both 2D and 3D, and in 2D in both the anti-plane (SH) and the in-plane (P-SV). The results show that the presence of a non-planar back wall can reduce the detectability of defects close to the surface. The...

  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

• 2011:19 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

• 2011:18 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