Filtered generated 146 hits.
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2016:09 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU – radionuclide transport, dose assessment, and safety analysis methodology
Initial review phase SSM English Initial review phase...
Content type: Publications -
2013:14 Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries – Evaluation for Regulatory Input
SSM has recently established new regulations for clearance of materials, rooms, buildings and land (SSMFS 2011:2). The regulations specify that license holders for practices involving ionising radiation shall take measures after the cessation of the practice to achieve clearance of rooms, buildings and land. The regulations state nuclide specific clearance levels in becquerel per m2 for rooms...
Content type: Publications -
2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C
SSM perspective Background The concept that the Swedish nuclear power industry plans to utilise for the final disposal spent nuclear fuel is called KBS-3 method, which is based on three different barriers to prevent spreading of radioactive substances: copper canisters, bentonite buffers and the surrounding Swedish bedrock. In the current KBS-3 design, the spent nuclear fuel will be placed in...
Content type: Publications -
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...
Content type: Publications -
2013:37 Technical Note, Rock Mechanics – Evolution of fracture transmissivity within different scenarios in SR-Site – Main Review Phase
The current review assignment consists of a literature review and independent modeling for assessing the importance of fracture transmissivity change especially driven by shear loading due to SKB’s thermal, glacial and earthquake loading scenarios for the KBS-3 repository at Forsmark. In the first part of the report, SKB’s laboratory experiments on shear fracture dilation and extensive...
Content type: Publications -
2013:20 Terrestrial Biosphere Modelling of C-14 Research
The need to address radiological impacts from 14C released to the biosphere has been recognized for some time. However, because of its role in biological processes and its ecological cycling, the standard methods employed to model long-term radionuclide transport and accumulation in the biosphere cannot be used satisfactorily for 14C. In 2011, the Swedish Radiation Safety Authority (SSM)...
Content type: Publications -
2014:08 Technical Note, Review of Long-Term Redox Evolution of Groundwater and Potential Influence of Oxygenated Glacial Meltwater in SR-Site
The Swedish Radiation Safety Authority (SSM) is reviewing an application submitted by the Swedish Nuclear Fuel and Waste Management Company (SKB) in 2011 to construct, possess, and operate a deep geologic repository for spent nuclear fuel at the Forsmark site in the municipality of Östhammar, Sweden. SKB has presented details of its long-term safety assessment, SR-Site, in a main report...
Content type: Publications -
2013:34 Technical Note, Seismology – Post-glacial seismicity and paleoseismology at Forsmark
Metoden som SKB använder för att förutse seismisk risk för slutförvaret skiljer sig i två avseenden från gängse förfarande. För det första, förkastningsrörelser inom förvaret är beräknade utifrån numeriska bergmekaniska modeller i stället för genom en Probabilistisk riskanalys för förkastningsrörelse...
Content type: Publications -
2014:11 Technical Note, Radionuclide Solubility Limits in SKB’s Safety Case
The Swedish Radiation Safety Authority (SSM) is reviewing a license application, which has been submitted by Svensk Kärnbränslehantering AB (SKB), for a spent nuclear fuel repository at Forsmark. This technical note records the findings from a project that forms part of the main phase of SSM’s license application review. The project involved review of reports and independent modelling...
Content type: Publications -
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...
Content type: Publications