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Din avgränsning ger 373 träffar.

• 2016:02 Technical Note, An updated review of the creep ductility of copper including the effect of phosphorus

  Background The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of a reposi-tory for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information on specific...

  Innehållstyp: Publikationer

• 2016:23 Technical Note, Modelling of the thermal evolution of the KBS-3 repository at Forsmark and associated induced seismic activity

  Main Review Phase Introduction The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of the KBS-3 repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain...

  Innehållstyp: Publikationer

• 2015:53 Ductile tearing – Micromechanical analyses and experimental study

  In this report, the project "Ductile Tearing-Micromechanical analyses and experimental study" is presented. In the project, numerical cell modeling has been conducted using the shear modified Gurson model proposed by Nahshon and Hutchinson to evaluate its capability in predicting the effect of residual stresses. Experimental work has also been conducted for material characterization.

  Innehållstyp: Publikationer

• 2016:05 Technical Note, Assessment of SKB TR-14-15 Assessment of SKB TR-14-15 “Possible influence from stray currents from high voltage DC power transmission on copper canisters”

  The general objective of the present project is to provide independent review comments for one area of SKB:s post closure safety analysis, SR-Site. With this in mind, the purpose of this report is to review SKB’s presentation on possible influence from stray currents from high voltage DC power transmission on a repository for nuclear fuel. Laust B Pedersen SSM English The general objective of...

  Innehållstyp: Publikationer

• 2016:09 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU – radionuclide transport, dose assessment, and safety analysis methodology

  Initial review phase...

  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

• 2018:05 Clab och inkapslingsanläggningen (Clink)

  Beredning inför regeringens prövning Slutförvaring av använt kärnbränsle...

  Innehållstyp: Publikationer

• 2014:38 Technical Note, Detailed assessment of radionuclide Kd-values for the geosphere-main review phase

  The Swedish Radiation Safety Authority (SSM) is reviewing an application submitted by the Swedish Nuclear Fuel and Waste Management Company (SKB) in 2011 to construct and operate a deep geologic repository for spent nuclear fuel at the Forsmark site in the municipality of Östhammar, Sweden. SKB has presented details of its long-term safety assessment, SR-Site, in a main report (SKB, 2011,...

  Innehållstyp: Publikationer

• 2018:03 Remissammanställning

  Beredning inför regeringens prövning Slutförvaring av använt kärnbränsle...

  Innehållstyp: Publikationer

• 2014:33 Technical Note, Reproduction of SKB’s Canister Failure Calculations - What-If and ‘Residual’ Scenario to Illustrate Barrier Functions

  The Swedish Nuclear Fuel and Waste Management Company (SKB) included analysis of a range of scenarios in its SR-Site report. SKB grouped these scenarios into two categories—main and residual. The main scenario included a likely scenario (corrosion failure) and a less probable scenario (seismicity-induced shear failure). The residual scenario included two unlikely scenarios—isostatic-load and...

  Innehållstyp: Publikationer