Filtered generated 754 hits.
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2017:30 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – consequence analysis
Background The Swedish Radiation Safety Authority (SSM) received an application for the expansion of SKB's final repository for low and intermediate level waste at Forsmark (SFR) on the 19 December 2014. SSM is tasked with the review of the application and will issue a statement to the government who will decide on the matter. An important part of the application is SKB’s assessment of...
Content type: Publications -
2017:11 Extended Common Load Model: A tool for dependent failure modelling in highly redundant structures
Background The treatment of dependent failures is one of the most controversial subjects in reliability and risk analyses. The difficulties are specially underlined in the case of highly redundant systems, when the number of redundant components or trains exceeds four. The Common Load Model (CLM), originally defined in the 70’ies, differs from other CCF models, as it relies on a specific...
Content type: Publications -
2008:18 Concerns when designing a safeguards approach for the back-end of the Swedish nuclear fuel cycle
Sweden has for many years collected the spent nuclear fuel originating from nuclear power plants. This fuel must at all times be kept under supervision to render a diversion impossible; this is of course due to the possibility to make weapons from the material. One idea is to keep the nuclear material in a repository deep under the ground; this is not only to keep the material safe from theft...
Content type: Publications -
2003:47 Field Test of a DCVD Using an Ixon Camera with a Lumogen-Coat EMCCD Detector
Canadian and Swedish Safeguard Support Programs J.D. Chen A.F. Gerwing R. Maxwell M. Larsson K. Axell L. Hildingsson B. Lindberg F. Vinna SKI English...
Content type: Publications -
00:23 Swedish Support Programme on Nuclear Non-Proliferation in Central and Eastern Europe and Central Asia
P. Ek (1), L. Wredberg (2), S. Andersson (1). (1) Swedish Nuclear Power Inspectorate, SE-106 58 Stockholm, Sweden. (2) ILG Consultant LTD, Hammerschmidtgasse 18/1, A-1190 Vienna, Austria. June 2000 SKI English...
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 -
2014:19 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 -
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 -
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 -
2013:04 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 18
The program executed in Stage 18 consists of the following three parts: Application of CoreSim with a two-dimensional model of vibrating fuel assemblies, for the calculation of ex-core detector noise throughout a fuel cycle; An investigation of the neutron noise, induced by propagating perturbations, in various thermal and fast reactor systems, in two-group theory; A consistent derivation of...
Content type: Publications