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This report has been prepared as part of the SSM’s Main Review Phase of SKB’s SR-Site performance assessment of the long-term safety of the KBS-3 geological disposal facility (GDF) proposed for construction at Forsmark. The review addresses the methodology employed in the dose assessment calculations of SR-Site; specifically issues of transport, accumulation and transfers of radionuclides in...

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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2014:21 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

2014:06 Dimensionering av nukleära byggnadskonstruktioner (DNB)

2014:01 Cost Estimating for Decommissioning Nuclear Reactors in Sweden

2014:35 Technical Note, Modelling comparison of alternative biosphere models with LDF models and evaluation of selected parameter values used in the biosphere dose assessment - Main review phase

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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