Din avgränsning ger 56 träffar.

• 2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock

  SSM perspective Background When assessing the long-term safety of a repository for spent nuclear fuel it is important to consider future earthquakes. Previous studies by Yoon et al. (2014, SSM Report 2014:59) and (2016, SSM Report 2016:23) investigated the fracture responses due to heat and

  Innehållstyp: Publikationer

• 2018:15 Review of Geochemical Data Utilisation in SR-Site Safety Assessment

  The Swedish Radiation Safety Authority (SSM) reviews and follows associated research related to the Swedish Nuclear Fuel Company’s (SKB) work with establishing a repository for spent nuclear fuel and an encapsulation facility.

  Innehållstyp: Publikationer

• 2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities

  Background Many practices involving radioactive substances generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions from a radiation

  Innehållstyp: Publikationer

• 2015:37 Models for axial relocation of fragmented and pulverized fuel pellets in distending fuel rods and its effects on fuel rod heat load

  Haverifall med kylmedelsförlust (LOCA) i lättvattenreaktorer kan leda till överhettning av bränslestavar, utvidgning av stavarnas kapslingsrör, samt axiell omflyttning av bränslekutsfragment i de delar av stavarna som expanderat. Bränsleomflyttningen kan koncentrera

  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.

  Innehållstyp: Publikationer

• 2013:07 Corrosion of copper in distilled water without molecular oxygen and the detection of produced hydrogen

  In this report, results are presented for copper which has been exposed to pure anoxic water in the temperature interval of 21 °C to 55 °C up to a total of 19 000 hours. Characterisations of copper surfaces after exposure have been performed ex-situ, meaning after termination of the experiment

  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

  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

  Innehållstyp: Publikationer

• 2011:34 Evolution of hydrogen by copper in ultrapure water without dissolved oxygen

  One result from this research was that the experimental difficulties of repeating Hultqvist and co-workers work are considerable and were initially underestimated. The main challenge was to obtain satisfactory tightness of all connectors involved in the experimental set-up. The problems with

  Innehållstyp: Publikationer

• 2011:26 The influence of temperature and fluid pressure on the fracture network evolution around deposition holes of a KBS-3V concept at Forsmark, Sweden

  In preparation for the review of SKB’s license application for disposal of spent nuclear fuel, 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

  Innehållstyp: Publikationer