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

  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

• 2014:19 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

• 2014:33 Technical Note, Reproduction of SKB’s Canister Failure Calculations - What-If and ‘Residual’ Scenario to Illustrate Barrier Functions

  The Swedish Nuclear Fuel and Waste Management Company (SKB) included analysis of a range of scenarios in its SR-Site report. SKB grouped these scenarios into two categories—main and residual. The main scenario included a likely scenario (corrosion failure) and a less probable scenario (seismicity-induced shear failure). The residual scenario included two unlikely scenarios—isostatic-load and...

  Content type: Publications

• 2014:22 Technical Note, Workshop on seismic hazard at Forsmark

  This report describes the outcome of the workshop organized by SSM on seismic hazard at Forsmark that was held in Stockholm on the 4 and 5 of June, 2013. The report summarizes the issues discussed and extracts the essential viewpoints that have been expressed. It should not be considered as a comprehensive record of all the discussions at the workshop and individual statements made by...

  Content type: Publications

• 2014:50 Technical Note, A Study of Availability of Fuel Data for Sweden’s Spent Nuclear Fuel

  The study covers all types spent fuel planned to be placed in the final repository. It was carried out by selecting a sample of spent fuel and investigating the information available at the Nuclear Power Plants (NPP’s) in Sweden, the Central interim storage facility (Clab) and Studsvik. The results indicate that the required data is available and can be obtained for fuel unloaded after 1980.

  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

• 2014:55 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

• 2014:46 Technical Note, QA in SKB’s Groundwater Flow Modelling

  The general objective of the project is to provide review comments on SKB’s postclosure safety analysis, SR-Site, for the proposed repository at Forsmark. The specific objective is to get an understanding and an assessment of SKB’s quality assurance of the groundwater flow modelling in connection to SR-Site. The reliability of the results of the groundwater flow modelling depends inter alia...

  Content type: Publications