Din avgränsning ger 143 träffar.
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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 -
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 -
2016:23 Technical Note, Modelling of the thermal evolution of the KBS-3 repository at Forsmark and associated induced seismic activity
Main Review Phase Introduction The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of the KBS-3 repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain...
Innehållstyp: Publikationer
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