Din avgränsning ger 25 träffar.
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2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022
The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2024:19 Finansiering av en minnesinstitution efter förslutning av slutförvar för använt kärnavfall
SSM perspektiv Bakgrund och syfte En central princip för dagens finansieringssystem för omhändertagandet av kärnämne och övrigt radioaktivt avfall som uppkommit vid drift och avveckling av kärnkraftverk är producentansvarsprincipen1. Ett finansieringssystem som grundas på en avgift per levererad kilowattimme till den s.k. Kärnavfallsfonden. I tillägg...
Innehållstyp: Publikationer -
2025:02 INCLUDE: Including (local) stakeholder participation in the regulatory mission – a future challenge
SSM perspektiv Bakgrund Det primära fokus för SSM:s kommunikation med intressenter i samband med slutförvaring av använt kärnbränsle och kärnavfall har under flera år legat på formella samrådsprocesser kring den svenska kärnkraftsindustrins forsknings- och utvecklingsprogram samt SKB:s tillståndsansökningar enligt kärntekniklagen.
Innehållstyp: Publikationer -
2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C
SSM perspektiv Bakgrund Den metod som den svenska kärnkraftsindustrin planerar att tillämpa för att slutförvara använt kärnbränsle kallas för KBS-3 och bygger på tre skyddsbarriärer: kopparkapslar, bentonitbuffert och det svenska urberget. I den aktuella KBS-3-utformningen kommer det använda kärnbränslet att placeras i en insats...
Innehållstyp: Publikationer -
2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository
Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish...
Innehållstyp: Publikationer -
2015:25 Design Guide for Nuclear Civil Structures (DNB)
The Swedish Radiation Safety Authority (SSM) and the Swedish licensees have previously in a jointly funded research project developed a design guide for civil structures at Swedish nuclear facilities to be based on Eurocodes, DNB. The report was published in January 2014 as SSM Report 2014:06. To further improve DNB and to ensure that the fundamentals of the recommendations will be applied...
Innehållstyp: Publikationer -
2013:28 Brine intrusion by upconing for a high-level nuclear waste repository at Forsmark. Scoping calculations
The objective of this study is to evaluate the possibility of salt-water migration to the spent nuclear repository. This objective is motivated by the adverse impacts of water with too high salinity entering the repository and by the uncertainty of the relevant hydraulic and hydrogeochemical conditions at the Forsmark site at great depths. To analyse density dependent flow and salt transport...
Innehållstyp: Publikationer -
2012:71 Identification of Brittle Deformation Zones and Weakness Zones
In preparation for the review of Swedish Nuclear Fuel and Waste Management Company’s (SKB) license application for disposal of spent nuclear fuel, Swedish Radiation Safety Authority (SSM) is conducting studies to evaluate the performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at...
Innehållstyp: Publikationer
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