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Our safety and security work
The role of the Swedish Radiation Safety Authority is to impose safety and security requirements as well as to conduct follow-ups to ensure that the entities operating the facilities fulfil the applicable regulatory frameworks and requirements.
Content type: Regular Pages -
2020:02 Models for axial gas flow and mixing in LWR fuel rods
SSM perspective Background Fission gases inside a fuel rod plays an important role in the behaviour of the fuel, both during normal operation and during events and accidents. Fission gases are released from inside the fuel pellets to the gap between the pellet and the cladding tube and then flow to the plenum volume at the top of the fuel rod. In high burnup fuel, this axial flow to the...
Content type: Publications -
2022:14 Weld residual stress and strain measurements on a mock-up with single layer strip cladding common in reactor pressure vessels
Summary Residual stress and strain measurements were performed on a mock-up consisting of a 160 mm thick low-alloy ferritic steel plate of type SA-508 Class 3 with a single layer weld deposited strip cladding of austenitic stainless steel E308L. The cladding was manufactured with submerged arc strip welding adapted to a procedure used for reactor pressure vessels in the 1970s. Comprehensive...
Content type: Publications -
2022:18 Data report – sampling of sea water and marine organisms outside Ringhals NPP
SSM perspective Background The Radiation Safety Authority (SSM) funded the collection of marine biota over an annual cycle at the Ringhals nuclear power plant (NPP) to enable development of analytical methods for C-14. Methods for the C-14 analysis and results in the form of levels of C-14 in various marine organisms have been reported by the Swedish Defense Research Institute (FOI) in FOI...
Content type: Publications -
2015:06 Technical Note, Feasibility of Backfilling Deposition Tunnels
SKB has been conducting an appropriate scientific and technical programme of research and development work to investigate the many processes that may affect the choice of backfill materials, the practicali- ties of backfill emplacement, and the properties of the emplaced backfill that may affect long-term radiological safety. On the basis of this re- search and development work SKB has outlined...
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 -
2012:36 Technical Note, Documentation and Traceability of Data in SKB’s Safety Assessment SR-Site: Initial Review Phase
On 16th March 2011SKB applied for a licence to construct and operate a spent nuclear fuel encapsulation facility in Oskarshamn Municipality and a final repository for the encapsulated fuel at Forsmark in Östhammar Municipality. SKB’s SR-Site safety assessment for the spent fuel repository is currently being reviewed by the Swedish Radiation Safety Authority, SSM, and its external experts...
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 -
2011:12 Analysis of Barrier Performance: Modelling of Copper corrosion scenarios with and without buffer erosion
The purpose of this project was to develop a numerical modelling capacity to address the corrosion of the copper canister under gradually changing transport conditions caused by buffer erosion and removal of buffer mass. Due to the complexity of this task, such a model cannot be realistic in all respects, but the present effort should address the feasibility of solving numerical and...
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