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• 2014:56 Seismic design and analysis of safety-related nuclear structures in Sweden

  The report presents the historical development of the seismic design for the U.S., France and Sweden with special focus on issues related to severe earthquakes beyond the design basis as well as important aspects concerning the design basis ground motions for the Swedish nuclear facilities. The report provides recommendations on a revised model for seismic hazard assessments, on minimum...

  Content type: Publications

• 2014:21 Effects of additives on uranium dioxide fuel behavior

  This report will form a basis for the reviews that SSM does when the license holders applies for use of nuclear fuel with additives. The report is also intended as a reference to the models that Quantum Technologies AB has developed. The report and the models will be a valuable source of information for SSM and other parties when discussing the performance of doped fuel. Ali Massih SSM...

  Content type: Publications

• 2014:20 An evaluation of high-temperature creep of zirconium alloys: data versus models

  In this report Dr Massih presents correlations for creep in different phases of zirconium alloys and also presents a general solution to the difficulty of accurately describing the material properties in phase transition for several zirconium alloys. Based upon superplasticity relations, models are adapted to fit with experimental data for materials in transition regions. The creep models are...

  Content type: Publications

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

  The analytical tools, which are fuel rod computer codes, that Quantum Technologies AB use and develop, contain models of several of the phenomena that are acting on the nuclear fuel (cladding temperature, fission gas driven pressure, strain and stress in the cladding, rod rupture, etc.) and how the separate effects interact in the complex integrated manner. The codes are under constant...

  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

• 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

• 2014:29 Technical Note, Independent Modelling of Radionuclide Transport, Evaluation of Colloid Transport Modelling – Main Review Phase

  SKB excludes consideration of colloids originating inside the canister in its performance assessment on the basis of the filtration capability of the buffer material. In the canister failure by corrosion scenario (central corrosion case), the buffer material is assumed eroded, and the filtration argument is not entirely valid for excluding modelling in-canister colloids. In this Technical...

  Content type: Publications

• 2014:24 Technical Note, Workshop on biosphere issues

  The objective of this workshop was to bring together experts in the field of radionuclide transport in the biosphere including non-human biota and dose assessment to discuss the findings of the detailed reviews performed during the main review phase and to identify any further biosphere review issues. This report describes the outcome of the workshop organized by SSM on Biosphere Issues that...

  Content type: Publications