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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

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

2014:10 Technical Note, Rock Mechanics - Confidence of SKB’s models for predicting the occurrence of spalling – Main Review Phase

This review study is placed in the context of SSM’s Main Review Phase for SKB’s safety assessment SR-Site. The assignment is titled “Rock Mechanics – Confidence of SKB’s models for predicting the occurrence of spalling”. The report presents the authors’ assessment in response to the questions raised by SSM. The review concentrated on two main issues: (1) the analysis of the assumptions made...

Content type: Publications

2014:32 Technical Note, Assessment of the derivation and use of distribution coefficients and concentration ratios – Main Review Phase

This report presents a review of the approaches and databases which SKB have used to derive concentration ratios (CRs) and distribution coefficients (Kds) to consider if they are robustly derived and fit for purpose. Credible alternative approaches are also considered. The focus of this review are SKB reports R-10-28 and TR-10-07 which describe the available site specific data and the...

Content type: Publications

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2014:28 Numerical simulation of ductile crack growth in residual stress fields

2014:21 Effects of additives on uranium dioxide fuel behavior

2014:19 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 5, 6 and 7

2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4

2014:09 Further Development of the Core Simulator CORE SIM: Extension to coupled capabilities for BWRs

2014:49 Samhällskostnader för hudcancer 2011

2014:08 Technical Note, Review of Long-Term Redox Evolution of Groundwater and Potential Influence of Oxygenated Glacial Meltwater in SR-Site

2014:11 Technical Note, Radionuclide Solubility Limits in SKB’s Safety Case

2014:10 Technical Note, Rock Mechanics - Confidence of SKB’s models for predicting the occurrence of spalling – Main Review Phase

2014:32 Technical Note, Assessment of the derivation and use of distribution coefficients and concentration ratios – Main Review Phase

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