Filtered generated 175 hits.
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2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay
SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...
Content type: Publications -
2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay heat and radiation, these materials are shipped to the Clab (Central Interim Storage...
Content type: Publications -
2023:07 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Increased storage of spent nuclear fuel at Clab in Sweden...
Content type: Publications -
2023:04 Kingdom of Sweden ARTEMIS Self-assessment Report 2023
Foreword In January 2018, the Swedish Radiation Safety Authority, SSM, submitted a request to the IAEA on behalf of the Swedish Government for international peer reviews to be conducted of the Swedish national frameworks for nuclear safety regulation (IRRS) and the safe management of spent fuel and radioactive waste (ARTEMIS). In dialogue with the IAEA, and in support of the then Swedish...
Content type: Publications -
2022:08 Geophysical surveys on sub marine land- and rock slides and on alpine glaciers
SSM perspective Background The future climate evolution and the impact it might have on a repository for radioactive waste is important when assessing the long-term safety. In a project funded by SSM (Holmlund et al. 2016), bathymetric data from the Southern Quark area between Sweden and Åland, provided by the Swedish Maritime Administration, were analysed, as well as terrestrial data from...
Content type: Publications -
2021:03 Updated radiological risk assessment for the “Radon” type surface disposal facility in Chisinau, Moldova
SSM perspective Background Bilateral cooperation between Sweden and the Republic of Moldova in nuclear and radiological safety and security has been ongoing since 2010, focusing on activities aimed at strengthening the institutional capacity of the National Agency for Regulation of Nuclear and Radiological Activities in Moldova (NARNRA) as well as infrastructure development in radioactive...
Content type: Publications -
2019:16 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU
– consequence analysis and hydrogeological aspects Main review phase...
Content type: Publications -
2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock
SSM perspective Background When assessing the long-term safety of a repository for spent nuclear fuel it is important to consider future earthquakes. Previous studies by Yoon et al. (2014, SSM Report 2014:59) and (2016, SSM Report 2016:23) investigated the fracture responses due to heat and earthquakes at major deformation zones using a 2D thermo-mechanical coupled model that uses a Particle...
Content type: Publications -
2018:15 Review of Geochemical Data Utilisation in SR-Site Safety Assessment
The objective of this study is to understand how data for groundwater compositions were used in producing the Site Descriptive Model for Forsmark and as input data for the safety assessment, SRSite. Improving this understanding sheds further light on the significance of data uncertainties, data processing and interpretation on the degree of uniqueness in the descriptive model, parameterisation...
Content type: Publications -
2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities
Background Many practices involving radioactive substances generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions from a radiation protection point of view. According to regulations issued by the SSM, such decisions must be based on...
Content type: Publications