Filtered generated 761 hits.
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2010:30 INSITE Summary Report
SSM and its predecessor SKI employed a team of earth scientists who followed and reviewed SKB’s investigations of the potential spent nuclear fuel repository sites at Forsmark and Laxemar. This group was named INSITE (INdependent Site Investigation Tracking and Evaluation) and began its work in 2002 and completed its task with the review of the final versions SKB’s site descriptive models,...
Content type: Publications -
2007:44e An Introduction to Nuclear Non-Proliferation and Safeguards
The compendium at hand will be used both within an outside Sweden as course material. It is partly a result from the work done by TKM (Training and knowledge management), which is a working group within Esarda (European Safeguards Research and Development Association) that on a yearly basis educates students from all over Europe. The intention is that the material shall be used in conjunction...
Content type: Publications -
2003:19 Nuclear Waste Separation and Transmutation Research with Special Focus on Russian Transmutation Projects Sponsored by ISTC
Henri Condé, Waclaw Gudowski, Jan Blomgren, Jan-Olov Liljenzin, Nils Olsson, Curt Mileikovsky, Jan Wallenius. March 2003 SKI English...
Content type: Publications -
2003:45 Cerenkov Characteristics of BWR Assemblies Using a Prototype DCVD With a Back-Illuminated CCD
Canadian and Swedish Safeguard Support Programs J.D. Chen, A.F. Gerwing, R. Maxwell, M. Larsson, K. Axell, L. Hildingsson, B. Lindberg, E. Sundkvist. November 2003 SKI English...
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 -
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 -
2013:29 Regulatory Approaches in Nuclear Power Supervision
The objective of this follow-up study was to support SSM in further understanding regulatory approaches and how they can be combined as part of effective strategies. The survey was intended to assist SSM in identifying current standards, experiences, and practices in the regulation of nuclear power plants. The results will also be valuable for the participating authorities as well as other...
Content type: Publications -
2013:10 Qualification of Electrical Equipment in Nuclear Power Plants - Management of ageing
The purpose of this report is to describe programs and tools for assessment of accomplished and documented qualification with respect to ageing of electrical equipment and for development of complimentary ageing management programs. In addition to description of complete programs for management of ageing, tools for validation of the status with regard to ageing of installed (“old”) equipment...
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