Publikationer

Din avgränsning ger 184 träffar.

• 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

• 2017:33 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – dose assessment, Kd-values, and safety analysis methodology

  Main review phase...

  Innehållstyp: Publikationer

• 2017:31 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – rock engineering and concrete barriers

  Main review phase...

  Innehållstyp: Publikationer

• 2017:30 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – consequence analysis

  Main review phase...

  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

• 2017:18 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