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Din avgränsning ger 12 träffar.

• SSMFS 2008:3 Strålsäkerhetsmyndighetens föreskrifter och allmänna råd om kontroll av kärnämne mm

  Du kan ladda ner eller beställa Strålsäkerhetsmyndighetens föreskrifter och allmänna råd (SSMFS 2008:3) om kontroll av kärnämne mm, se nedan. Vid beställning av den här föreskriften får du den konsoliderade...

  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...

  Innehållstyp: Publikationer

• 2012:61 Geochemical Constraints on Buffer Pore Water Evolution and Implications for Erosion

  Mineralogical data from the Forsmark Site show that smectite and calcite occur at all depths in Forsmark fractures, with no evidence for removal/dissolution by previous glacial episodes.  This natural analogue information implies that these minerals may not have been eroded/dissolved during previous glacial episodes. Available thermodynamic data suggest that repository-depth Forsmark...

  Innehållstyp: Publikationer

• 2012:11 Issues in the corrosion of copper in a Swedish high level nuclear waste repository

  The objective with this research project was to increase knowledge in the area of copper corrosion in the planned repository environment and obtain information on how copper corrosion evolves during the assessment period of 100 000 years.  The equilibrium chemical composition of groundwater close to the canister as a function of temperature has been calculated by use of a thermodynamics...

  Innehållstyp: Publikationer

• 2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository

  canisters fail during different time spans after closure of the repository (e.g. from 1 to 300, 1 to 1 000, 1 to 6 000 and 1 to 100 000 years) using the earlier developed isostatic load model. The investigation ... extreme scenarios resulted in doses less than the typical background radiation in Sweden (approximately 1 mSv/yr). The results can be used by simply scaling the results of the bounding case calculations to...

  Innehållstyp: Publikationer

• 2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022

  The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022 ... first IRRS peer review in Sweden, after the Nuclear Safety Directive came into force, was conducted in 2012 with a follow-up mission in 2016. A preparatory meeting was held with IRRS mission representatives...

  Innehållstyp: Publikationer

• 2017:02 Slow strain rate testing of copper in sulfide rich chloride containing deoxygenated water at 90 °C

  Background Stress corrosion cracking (SCC) can occur in materials from the combined ... containing water at a sulfide concentration of ~1·10−3 M and at a true stress threshold value of approximately 160 MPa. At lower sulfide concentration (~1·10−4 M), no SCC was observed on specimens. To some...

  Innehållstyp: Publikationer

• 2024:02 Earthquake stationarity and distributed fault displacements, Forsmark repository site

  och (mindre) modellerade förskjutningarna, eftersom de mäter olika fenomen. Rekommendationer Fråga 1 – Etablera hur PFC-modellering av inducerade förkastningsrörelser (som matchar empiriska förskjutningar) ... sprickorna i PFC-modellen? Och om inte det, vad orsakar skillnaden? Fråga 2 – Efter att ha besvarat fråga 1, kan 3DEC-modellering reproducera observerade sekundära förkastningsrörelser? Fråga 3 – Om ytterligare...

  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 ... downconing) following closure of the repository is also evaluated. In particular the objectives are (1) to determine the factors that control saltwater upconing in a hydrogeological setting representative...

  Innehållstyp: Publikationer

• 2018:21 Research on Resaturation of Bentonite Buffer

  judgement of the long-term safety of spent fuel repository. Results This report consists of three parts: (1) Research on Resaturation of Bentonite Buffer – Hydrological Modelling; (2) Research on Resaturation ... fracture transmissivity. Excavation-induced fractures would be encountered only in the upper 0.5 to 1 m of a deposition hole. Thermally induced spalling could result in a spalled zone up to 10 cm deep and...

  Innehållstyp: Publikationer