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Filtered generated 35 hits.

• 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

• 2014:56 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

• 2014:20 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

• 2014:21 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

• 2014:08 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

• 2014:54 Technical Note, Further Modelling Comparison of Simple Reference Biosphere Models with the LDF Modelling Approach – Main Review Phase

  This Technical Note describes further use of simple reference biosphere models for SSM’s review of the Landscape Dose Factor (LDF) approach adopted by SKB in the SR‑Site safety assessment for the proposed final disposal of spent nuclear fuel at the Forsmark site. Simple biosphere models for the Forsmark site under temperate climate conditions were previously developed for SSM’s review and are...

  Content type: Publications

• 2014:58 Technical Note, Rock Mechanics - Assessing probability and extent of blind faults and fault-end growth around the KBS-3 repository at Forsmark – Main Review Phase

  To get a general understanding of the stability conditions of the fault and deformation zone inventory at Forsmark a reactivation potential analysis was carried out. At present-day stress conditions the deformation zones are stable and show no large deformations or detected seismicity. Any changes in stress, and in particular increase of differential stress on deformation zones, might cause...

  Content type: Publications

• 2014:47 Technical Note, Assessment of groundwater salinity evolution at repository depth and especially the impact of dilute water infiltration

  Groundwater compositions entering deposition holes in the repository will be progressively diluted over time because of expected changes of topographic and climatic conditions at Forsmark. This is a long-term safety issue because very dilute water could destabilise compacted bentonite and erode buffer, leading to advective movement of sulphide-containing water to the canister surface. SKB’s...

  Content type: Publications

• 2014:55 Technical Note, Further Reproduction of SKB’s Calculation Cases and Independent

  Som en del av säkerhetsanalysen SR-Site presenterar SKB modellresultat som illustrerar kapseln och buffertens säkerhetsfunktioner. I var och en av de fem beräkningsfallen är delar av kapsel och/eller buffert frånvarande i modellen av slutförvarssystemet. Modellresultaten jämförs inte med säkerhetskriterier eftersom beräkningsfallen innehåller...

  Content type: Publications

• 2014:44 Technical Note, Independent evaluation of the number of critical canister positions in the KBS-3 repository at Forsmark – Main Review Phase

  Independent calculations were carried out to estimate Ncrit, the number of canisters in critical positions that can be expected in the proposed repository at Forsmark, based on statistical simulations of SKB's geological discrete-fracture network (Geo-DFN) models, and taking into account SKB's full-perimeter criterion (FPC) and extended full-perimeter criterion (EFPC) to screen out...

  Content type: Publications