Filtered generated 144 hits.
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2024:06 In search of lost storms: or can one infer the magnitudes of extremely rare flood events from short observational records?
Magnus Hieronymus SSM English...
Content type: Publications -
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 -
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 -
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 -
2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022
The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022...
Content type: Publications -
2022:09 Assessment of modelling approaches for axial gas flow inside LWR fuel rods
SSM perspective Background The fuel rod analysis program SCANAIR has been developed by IRSN (Institut de Radioprotection et de Sûreté Nucléaire) for analysis of reactivity initiated accidents (RIA) in light water reactors. The Swedish Radiation Safety Authority (SSM) has access to SCANAIR in exchange for annual contributions for its further development. The development...
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 -
2022:04 Warm Pre-Stressing mechanisms
SSM perspective Background Swedish nuclear power plants (NPP) were originally designed and analyzed with an assumed operating period of approximately 40 years. As Swedish NPPs reach their original technical design life the safety of the additional operating time has to be verified. With increased operating time, the shift in the fracture toughness curve of the reactor pressure vessel (RPV)...
Content type: Publications -
2022:03 Effect of Neutron Irradiation on the Oxidation and Corrosion of Austenitic Stainless Steels
SSM perspective Background Reactor pressure vessel internal components of austenitic stainless steel located close to the core are subject to a high neutron flux. Irradiation by fast neutrons induces changes in the material that affect microstructure, mechanical properties and microchemistry. These changes eventually lead to an increased susceptibility to irradiation assisted stress corrosion...
Content type: Publications