Filtered generated 761 hits.
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2004:08 Transparency and Public Participation in Radioactive Waste Management
Kjell Andersson, Magnus Westerlind, Elizabeth Atherton, Francois Besnus, Stéphane Chataîgnier, Saida Engström, Raul Espejo, Tim Hicks, Björn Hedberg, Jane Hunt, Ales Laciok, Antti Leskinen, Christina Lilja, Mike O'Donoghue, Sandrine Pierlot, Clas-Otto Wene, Juhani Vira, Roger Yearsley SKI English...
Content type: Publications -
98:29 Design Basis for the Copper/Steel Canister, Stage four, Final Report
W. H. Bowyer SKI English...
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 -
2012:63 Technical Note, Review of Radionuclide Sorption on Bentonite and Forsmark Bedrock Material
Denna rapport granskar sorption-data för bentonit och berg vilka har använts i säkerhetsanalysen SR-Site. Det kan konstateras att härledningen av Kd-värden har gjorts på ett systematiskt sätt och att presentationen av resultat är uttömmande. Kontroller visar att härledning och överföring av resultat kan betraktas som spårbar. Det...
Content type: Publications -
2012:58 Technical Note, Independent radionuclide transport modelling – Reproducing results for main scenarios
As part of the initial technical review of SR-Site, we applied a simplified model to approximate Swedish Nuclear Fuel and Waste Management Company (SKB) computations related to the transport of radionuclides at the planned KBS–3 repository at the Forsmark site in Sweden. The objective was to provide insights and recommendations to the Swedish Radiation Safety Authority (SSM) on potential...
Content type: Publications -
2012:60 Technical Note, Handling of climate related issues in the safety assessment SR-Site
The application is based on research carried out over several decades and is an impressive compilation of data and knowledge of the site of Forsmark. The sections on climate, glaciations and permafrost have developed continuously through the earlier compilations reported (e.g. the SR-97-reports). Much has been improved over the years while new question marks have occurred and some known...
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 -
2013:07 Corrosion of copper in distilled water without molecular oxygen and the detection of produced hydrogen
In this report, results are presented for copper which has been exposed to pure anoxic water in the temperature interval of 21 °C to 55 °C up to a total of 19 000 hours. Characterisations of copper surfaces after exposure have been performed ex-situ, meaning after termination of the experiment and exposing the specimen to normal atmospheric environment. Ideally characterisation of surfaces...
Content type: Publications