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Din avgränsning ger 111 träffar.

• 2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents

  Ali R. Massih, Lars Olof Jernkvist SSM English...

  Innehållstyp: Publikationer

• SSMFS 2018:2 Strålsäkerhetsmyndighetens föreskrifter om anmälningspliktiga verksamheter

  SSMFS 2018:2 har upphävt SSMFS 2008:5, 2008:40 och 2012:1. I SSMFS 2018:2 har ändringar förts in genom SSMFS 2019:1, SSMFS 2019:4 och SSMFS 2025:2.

  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

• 2018:21 Research on Resaturation of Bentonite Buffer

  Background Resaturation processes in the bentonite buffer in a KBS-3 type repository for spent nuclear fuel are complicated and are often illustrated, analysed and modelled multi-disciplinarily as coupled thermal (T), hydrological (H) and mechanical (M) processes with multi-phase flow, elastoplastic evolution in a swelling porous medium. Previous THM-modelling showed that the re-saturation...

  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

• 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

• 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 leakage resulted in that the research program originally planned for in this project had to be reduced...

  Innehållstyp: Publikationer

• 2010:43 Displacement along extensive deformation zones at the two SKB sites: Forsmark and Laxemar

  The Fennoscandian shield is distinguished by that the exposed bedrock is mainly composed of Precambrian metamorphic and igneous rocks older than a billion or one and a half billion years with few easily distinguished testimonies for the younger history. Large parts of the present ground surface closely coincides with a late Precambrian denudation surface; the sub-Cambrian peneplain.

  Innehållstyp: Publikationer

• 2011:09 Is Copper Immune to Corrosion When in Contact With Water and Aqueous Solutions?

  The KBS-3concept implies that spent nuclear fuel is placed in copper canisters surrounded by clay and finally placed approximately 500 m down from surface into granitic bedrock, in order to isolate the spent nuclear fuel from humans and environment for very long time scales (i.e. millions of years). The concept is based on the multi-barrier principle, in this respect the barriers are the...

  Innehållstyp: Publikationer