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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 -
2023:02 Investigation of risk assessment for decommissioning waste to Fortum’s landfill at Norrtorp
Shulan Xu, Ryk Klos SSM English...
Content type: Publications -
2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022
The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022...
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 -
2021:19 Importance Sampling Time-Domain Random Walk (ISTIDRAW) Version 1.0 User Guide A Code for Radionuclide Transport in Pathway Networks
SSM perspective Background To support regulatory review of post-closure safety assessments of geological disposal systems it is of importance to possess regulatory independent modelling capacity. Typically, SSM’s independent modelling includes performing simple scoping calculations, utilizing the implementer’s own models with other equation solvers, or defining alternative conceptual models.
Content type: Publications -
2021:14 Reliability, Feasibility and Significance of Measurements of Conductivity and Transmissivity of the Rock Mass for the Understanding of the Evolution of a Repository of Radioactive Waste
SSM perspective Background The conducted research was part of the international research project DECOVALEX 2019 (DEvelopment of COupled models and their VALidation against EXperiments). DECOVALEX 2019 consisted of seven different research projects called Task A to G. SSM were involved in Task G, which were composed of three different teams from Technical University of Liberec (TUL), Seoul...
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2021:13 SSM’s external experts’ review of SKB’s safety evaluation SE-SFL
SSM perspective Background In Sweden long-lived low- and intermediate level radioactive waste is planned to be disposed in a repository (SFL) in the Swedish crystalline rock at a depth around 500 m. The waste contains mainly the long-lived wastes from the operation and decommissioning of the Swedish nuclear reactor plants, as well as the long-lived wastes from early research in the Swedish...
Content type: Publications -
2021:06 Quality Assurance Review of the Swedish Nuclear Fuel and Waste Management Company’s LOT Experiment (Phase S2 and A3) at the Äspö Facility in Sweden
SSM perspective Background This report presents a quality assurance (QA) review of the work done by SKB to retrieve the S2 and A3 parcels from the Long term test of buffer material (the LOT experiment) at the Äspö Hard Rock Laboratory. Each LOT parcel comprises a heated copper tube surrounded by bentonite, with a number of copper coupons and various other test and monitoring instruments...
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 -
2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C
SSM perspective Background The concept that the Swedish nuclear power industry plans to utilise for the final disposal spent nuclear fuel is called KBS-3 method, which is based on three different barriers to prevent spreading of radioactive substances: copper canisters, bentonite buffers and the surrounding Swedish bedrock. In the current KBS-3 design, the spent nuclear fuel will be placed in...
Content type: Publications