Filtered generated 215 hits.
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2021:05 Cladding tube rupture under LOCA: Data and models for rupture opening size
SSM perspective Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance closely. One aspect that is currently being studied in several research projects is the risk of release of fragmented fuel into the primary coolant in case of an accident. This risk depends on complex conditions were one is the possibility and size of a rupture of the fuel rod...
Content type: Publications -
2017:16 Stress intensity factor solutions for circumferential cracks in cylindrical bars under axisymmetric loading and global bending
Background The case of a circumferential crack in a cylindrical bar has not been available in the ProSACC code. The need for such a geometry, especially considering nonlinear axisymmetric loading and global bending, has motivated the development of new stress intensity factor solutions, also known as K-solutions. These new K-solutions will be available in ISAAC, the successor to ProSACC.
Content type: Publications -
2021:01 In situ NMR condition monitoring of cable insulations in Nuclear Power Plants
Prof. István Furó, Dr. Payam Pourmand, Dr. Pavel Yushmanov SSM English...
Content type: Publications -
2010:41 Rock-block configuration in Uppland and the Ålands-hav basin, the regional surroundings of the SKB site in Forsmark, Sea and land areas, eastern Sweden
This report concerns a study which was initially conducted for the Swedish Nuclear Power Inspectorate (SKI), which is now merged into the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the SSM. The topography in Uppland is more broken in the sea area east and northeast of...
Content type: Publications -
2009:30 A Review of Evidence for Corrosion of Copper by water
The planned spent nuclear fuel repository in Sweden relies on a copper cast iron canister as the primary engineered barrier. The corrosion behaviour of copper in the expected environment needs to be thoroughly understood as a basis for the post-closure safety analysis. It has been shown that corrosion may indeed be the primary canister degradation process during the utilised assessment period...
Content type: Publications -
2007:17 Spent Fuel Dissolution and Source Term Modelling in Safety Assessment
SKI is preparing to review the license applications being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB) for a final repository for the geological disposal of spent nuclear fuel (SFL-2) in the year 2009. As part of its preparation, SKI is conducting a series of technical workshops on key aspects of the Engineered Barrier System (EBS) and spent fuel. This workshop...
Content type: Publications -
2010:40 Rock-block characterization on regional to local scales for two SKB sites in Forsmark – Uppland and Laxemar – eastern Småland, south-eastern Sweden
To get an overall impression of the general structural setting of a landscape, a remote study of bedrock structures should include studies of the geomorphology at various scales. Thematic maps improve the general understanding of an area. Digital elevation data in 500m, 50m and 10m grids were used for rock-block interpretations at regional, semi-regional and local scales of areas around the...
Content type: Publications -
2010:38 The feasibility of Backfilling a Repository of Spent Fuel: An Assessment of Recent Developments by SKB
In the Review Statement and Evaluation of SKB’s RD & D programme 2007 (SKI Report 2008:48E), the former Swedish Nuclear Power Inspectorate (SKI) commented that considerable work remained to be done for knowledge of both practical management issues on backfilling and analysis of long-term backfill evolution to reach the same level as for the canister and the buffer. SKI considered that the...
Content type: Publications -
2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code
The aim of this applied study has been to describe in a systematic way an appropriate methodological sequence for cost estimation of crucial parameters in decontamination and decommission processes. The work has been limited to older nuclear installations and facilities. Furthermore, it may be envisaged that the process of estimating the parameters of decommissioning is one of the main issues...
Content type: Publications -
2010:34 The understanding of the formation of valleys and its implication on site characterization: Moredalen and Pukedalen, south-eastern Sweden
This report concerns a study which was initially conducted for the Swedish Nuclear Power Inspectorate (SKI), which is now merged into the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the SSM. In south-eastern Sweden, there are a number of over-deepened narrow valleys,...
Content type: Publications