Showing 3315 hits for ””
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2004:56 Whiskers and Localized Corrosion on Copper in Repository Environment
Hans-Peter Hermansson, Peter Gillén SKI English...
Content type: Publications -
2003:23 Creep of the Copper Canister A Critical Review of the Literature
William H. Bowyer SKI English...
Content type: Publications -
98:41 Statistical Patterns of Geochemistry in Crystalline Rock and Effect of Sorption Kinetics on Radionuclide Migration
S. Xu, A. Wörman SKI English...
Content type: Publications -
01:38 Galvanic and Stress Corrosion of Copper Canisters in Repository Environment. A Short Review
Hans-Peter Hermansson, Martin König SKI English...
Content type: Publications -
01:04 SKI and SSI's Joint Review of SKBs Safety Assessment
SKI,SSI English...
Content type: Publications -
2013:08 Licensing of safety critical software for nuclear reactors
It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, i.e. the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors.
Content type: Publications -
2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...
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 -
2017:37 Non-Ionising Radiation in Swedish Health Care
Jonna Wilén, Kjell Hansson Mild, Ronnie Lundström SSM English...
Content type: Publications