Din avgränsning ger 278 träffar.
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2015:08 Technical Note, Rheological properties of the Bentonite Buffer
Objectives of the project The general objective of the project is to provide review comments on SKB’s postclosure safety analysis, SR-Site, for the proposed repository at Forsmark. This technical note reviews SKB:s reporting of the rheological and geomechanical properties of buffer bentonite, both at high and low densities. Göran Sällfors, GeoForce AB, Göteborg SSM English Objectives of...
Innehållstyp: Publikationer -
2015:41 Technical Note, Hydrogeological aspects of future human actions for a repository at Forsmark
Joel E. Geier SSM English...
Innehållstyp: Publikationer -
2014:57 Technical Note, Issues in the Corrosion of Copper in a Swedish High Level Nuclear Waste Repository: Phase III. Role of Sulphide Ion in Anodic and Cathodic Processes
The most important findings of this research project show that: In the case when the bentonite buffer between the copper canister and the granitic rock is not damaged, we can neglect the possibility of general corrosion damage being a threat to canister integrity over a 100,000 year storage period. However, if the bentonite buffer is damaged for any reason, and does not act as an engineered...
Innehållstyp: Publikationer -
2014:48 Technical Note, Independent assessment of groundwater sulphide content in the long-te
Groundwater sulphide content is a key factor in the determination of canister lifetimes because of its role in corrosion of copper. SKB has based the canister lifetime analysis on a distribution of measured sulphide concentrations which are assumed to apply throughout the long-term analysis period. The distribution is based on expert judgement in the selection of samples that are regarded as...
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 -
2017:33 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 -
2017:30 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – consequence analysis
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 -
2014:50 Technical Note, A Study of Availability of Fuel Data for Sweden’s Spent Nuclear Fuel
The study covers all types spent fuel planned to be placed in the final repository. It was carried out by selecting a sample of spent fuel and investigating the information available at the Nuclear Power Plants (NPP’s) in Sweden, the Central interim storage facility (Clab) and Studsvik. The results indicate that the required data is available and can be obtained for fuel unloaded after 1980.
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
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