Rapporter

Din avgränsning ger 40 träffar.

• 2017:25 Evaluation of weld fatigue reduction in austenitic stainless steel pipe components

  Background The performed investigation is a continuation of the work performed in SSM 2015:38 where fatigue tests were performed on pressurized welded austenitic stainless steel piping components. The specimens were subjected to a realistic variable amplitude loading with mainly reversed bending deformation and particular focus on high cycle fatigue. The previous fatigue results were quite...

  Innehållstyp: Publikationer

• 2017:24 Action Week – Granskning av berättigandeprocessen

  Sammanfattning I november 2016 genomförde Strålsäkerhetsmyndigheten (SSM) tillsammans med 17 andra europeiska länder en granskning av berättigandeprocessen inom röntgendiagnostik. Granskningen gick under namnet "Action Week" och involverade 15 radiologiska kliniker i Sverige och totalt 142 kliniker i Europa. Syftet med granskningen var att öka medvetenheten...

  Innehållstyp: Publikationer

• 2017:23 Kalibrering för bestämning av optimal beräkningsmodell

  Bakgrund SSM bedömer i tillsynen avancerade datorberäkningar relaterade till drift av kärnkraftverk, utförda av extern part. Inom kärnkraft kan experimentella undersökningar vara olämpliga. Beräkningar blir därför ofta det enda alternativet att undersöka möjliga konsekvenser av planerade förändringar. Beräkningsmodeller...

  Innehållstyp: Publikationer

• 2017:22 Effect of weld repairs on residual stresses in nickel base dissimilar metal welds

  Background The driving force for crack growth near welds in nuclear application piping may arise from weld residual stresses. Experience from nondestructive examination show that cracks in dissimilar metal welds are often found near weld repairs. The repair welding may affect the residual stresses through e.g. increased tensile stresses and increased plastic straining on the surfaces of the...

  Innehållstyp: Publikationer

• 2017:21 Neutronfluensberäkningar för surveillance provning

  Sammanfattning Bestrålning av reaktortankens material med snabba neutroner leder till förändringar i materialets egenskaper så att det försprödas. De förändrade materialegenskaperna utgör en av de viktigaste orsakerna till att reaktortankens livslängd är begränsad. Att kunna beräkna det totala neutronflödet som reaktortanken...

  Innehållstyp: Publikationer

• 2017:20 Assessment of inertia effects on transient clad-to-coolant heat transfer and coolant flow under reactivity initiated accidents

  In this report, simple hydrodynamic models are used for studying the effects of coolant inertia on fuel-to-coolant heat transfer and coolant flow under reactivity initiated accidents in light water reactors. The objective is to assess if the inertia effects are important enough to warrant modification of QT-COOL, a coolant channel module for two-phase flow that has recently been implemented as...

  Innehållstyp: Publikationer

• 2017:19 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures, Phase 2

  Background In the design of anchorage equipment in concrete structures the beneficial effects of reinforcement are, in most cases, not considered. The American ASCI 349-06 code opens up for a more detailed analysis where the beneficial impact of reinforcement on anchor capacity can be taken into account. How this analysis can be done is, however, not explicitly described in the code. The...

  Innehållstyp: Publikationer

• 2017:18 FEM analysis of the mechanical integrity for the canister intended for storage of spent nuclear fuel with regard to copper creep ductility

  Background For final storage of spent nuclear fuel it is suggested by the Swedish nuclear fuel and waste management company (SKB) to emplace the nuclear fuel into copper canisters which are surrounded by bentonite clay at approximately 500 meters’ depth into granitic rock. After emplacement of the canisters Bentonite swelling due to water saturation and hydrostatic pressure build up the...

  Innehållstyp: Publikationer

• 2017:17 Granskning och utvärdering av SKB:s redovisning av Fud-program 2016

  Strålsäkerhetsmyndighetens yttrande Svensk Kärnbränslehantering AB (SKB) har lämnat in Fud-program 2016 till Strålsäkerhetsmyndigheten (SSM) för granskning och utvärdering enligt 12 § lagen 1984:3) om kärnteknisk verksamhet kärntekniklagen). SSM föreslår att regeringen beslutar att reaktorinnehavarna genom SKB:s redovisning...

  Innehållstyp: Publikationer

• 2017:16 Stress intensity factor solutions for circumferential cracks in cylindrical bars under axisymmetric loading and global bending

  Background The case of a circumferential crack in a cylindrical bar has not been available in the ProSACC code. The need for such a geometry, especially considering nonlinear axisymmetric loading and global bending, has motivated the development of new stress intensity factor solutions, also known as K-solutions. These new K-solutions will be available in ISAAC, the successor to ProSACC.

  Innehållstyp: Publikationer