Publikationer

Din avgränsning ger 77 träffar.

• 2021:03 Updated radiological risk assessment for the “Radon” type surface disposal facility in Chisinau, Moldova

  SSM perspective Background Bilateral cooperation between Sweden and the Republic of Moldova in nuclear and radiological safety and security has been ongoing since 2010, focusing on activities aimed at strengthening the institutional capacity of the National Agency for Regulation of Nuclear and Radiological Activities in Moldova (NARNRA) as well as infrastructure development in radioactive...

  Innehållstyp: Publikationer

• 2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C

  SSM perspektiv Bakgrund Den metod som den svenska kärnkraftsindustrin planerar att tillämpa för att slutförvara använt kärnbränsle kallas för KBS-3 och bygger på tre skyddsbarriärer: kopparkapslar, bentonitbuffert och det svenska urberget. I den aktuella KBS-3-utformningen kommer det använda kärnbränslet att placeras i en insats...

  Innehållstyp: Publikationer

• 2018:21 Research on Resaturation of Bentonite Buffer

  Background Resaturation processes in the bentonite buffer in a KBS-3 type repository for spent nuclear fuel are complicated and are often illustrated, analysed and modelled multi-disciplinarily as coupled thermal (T), hydrological (H) and mechanical (M) processes with multi-phase flow, elastoplastic evolution in a swelling porous medium. Previous THM-modelling showed that the re-saturation...

  Innehållstyp: Publikationer

• 2018:15 Review of Geochemical Data Utilisation in SR-Site Safety Assessment

  The Swedish Radiation Safety Authority (SSM) reviews and follows associated research related to the Swedish Nuclear Fuel Company’s (SKB) work with establishing a repository for spent nuclear fuel and an encapsulation facility.

  Innehållstyp: Publikationer

• 2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities

  Background Many practices involving radioactive substances generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions from a radiation protection point of view. According to regulations issued by the SSM, such decisions must be based on...

  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

• 2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository

  Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish...

  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

• 2016:30 Measurement of Parameter Values for Predicting Corrosion Phenomena on Copper in Swedish HLNW Repositories

  Passivity breakdown and pitting on pure copper, the assumed material for the canisters for the isolation of high-level nuclear waste in Sweden, has been studied in simulated, sulphide- and chloride containing granitic rock groundwater and the data are interpreted in terms of the Point Defect Model (PDM). The results indicated that a sulphide barrier layer forms on the copper surface, and that...

  Innehållstyp: Publikationer

• 2016:21 The effect of a glaciation on East Central Sweden: case studies on present glaciers and analyses of landform data

  The Swedish Radiation Safety Authority reviews and assesses applications for geological repositories for nuclear waste. When assessing the long term safety of the repositories it is important to consider possible future developments of climate and climate-related processes. Especially the next glaciation is important for the review and assessment for the long term safety of the spent nuclear...

  Innehållstyp: Publikationer