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Din avgränsning ger 60 träffar.

• Så här kan man stoppa joniserande strålning

  Faktabladet beskriver vilka material som stoppar alfa-, beta- och gammastrålning.

  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

• 2017:02 Slow strain rate testing of copper in sulfide rich chloride containing deoxygenated water at 90 °C

  Background Stress corrosion cracking (SCC) can occur in materials from the combined influence of tensile stress and a corrosive environment. It has previously been shown in the literature, that copper can be sensitive to SCC in the presence of sulfide containing water. Since both tensile...

  Innehållstyp: Publikationer

• 2017:28 SSM’s external experts’ review of SKB’s safety assessment SR-PSU - hydrogeology, geochemistry and bentonite

  Main review phase...

  Innehållstyp: Publikationer

• 2017:09 Evaluation of the Swedish participation in the Nordic Nuclear Safety Research (NKS) collaboration

  Background NKS is a Nordic collaboration promoting cooperation on nuclear safety and emergency preparedness research. The research program is primarily funded by Nordic radiation safety authorities and responsible ministries. The main purpose of NKS is to finance joint Nordic activities and initiatives, including seminars and workshops, technical reports, exercises and scientific articles.

  Innehållstyp: Publikationer

• 2017:05 Robust structural verification of pressurized nuclear components subjected to ratcheting, part two – stress-strain curves for cyclic elastoplastic analysis.

  Background Pressurized components in nuclear applications that are subjected to cyclic loading may exhibit progressive deformation, so called structural ratcheting. If the component is made out of a material that are deformation hardening, it may also exhibit material ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material...

  Innehållstyp: Publikationer

• 2017:07 Dimensionering av nukleära byggnadskonstruktioner (DNB)

  Bakgrund Strålsäkerhetsmyndigheten (SSM) och de svenska tillståndshavarna har tidigare i ett samfinansierat forskningsprojekt tagit fram anvisningar för dimensionering av nukleära byggnadskonstruktioner, DNB. Rapporten som är baserad på Eurokoderna publicerades som SSM rapport 2014:06. DNB har sedan dess genomgått en generell uppdatering och publicerades...

  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