Filtered generated 164 hits.
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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 -
2022:04 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 -
2022:09 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 and administration...
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 -
2022:14 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 -
SSMFS 2022:2 Strålsäkerhetsmyndighetens allmänna råd om tillämpningen av föreskrifterna (SSMFS 2008:1) om säkerhet i kärntekniska anläggningar
226 kB...
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SSMFS 2008:38 Strålsäkerhetsmyndighetens föreskrifter om arkivering vid kärntekniska anläggningar (ursprunglig version)
118 kB...
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SSMFS 2022:12 Föreskrifter om ändring i Strålsäkerhetsmyndighetens föreskrifter (SSMFS 2008:38) om arkivering vid kärntekniska anläggningar
28 kB...
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SSMFS 2008:38 Strålsäkerhetsmyndighetens föreskrifter om arkivering vid kärntekniska anläggningar (konsoliderad version)
168 kB...
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SSMFS 2008:32 Strålsäkerhetsmyndighetens föreskrifter och allmänna råd om kompetens hos driftpersonal vid reaktoranläggningar (ursprunglig version)
176 kB...
Content type: Documents