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Din avgränsning ger 168 träffar.

• 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

• 2014:41 Technical Note, Review of Radionuclide Abstraction and Selection in the SKB Safety Case -Main Review Phase

  As part of the Swedish Radiation Safety Authority (SSM) review of the Swedish Nuclear Fuel and Waste Management Company (SKB) SR-Site safety assessment for a spent nuclear fuel repository in Sweden, this technical note documents the Center for Nuclear Waste Regulatory Analyses (CNWRA®) review of the abstraction and selection of radionuclides in the SKB safety case. Specifically, CNWRA...

  Innehållstyp: Publikationer

• 2014:57 Technical Note, Issues in the Corrosion of Copper in a Swedish High Level Nuclear Waste Repository: Phase III. Role of Sulphide Ion in Anodic and Cathodic Processes

  The most important findings of this research project show that: In the case when the bentonite buffer between the copper canister and the granitic rock is not damaged, we can neglect the possibility of general corrosion damage being a threat to canister integrity over a 100,000 year storage period. However, if the bentonite buffer is damaged for any reason, and does not act as an engineered...

  Innehållstyp: Publikationer

• 2014:48 Technical Note, Independent assessment of groundwater sulphide content in the long-te

  Groundwater sulphide content is a key factor in the determination of canister lifetimes because of its role in corrosion of copper. SKB has based the canister lifetime analysis on a distribution of measured sulphide concentrations which are assumed to apply throughout the long-term analysis period. The distribution is based on expert judgement in the selection of samples that are regarded as...

  Innehållstyp: Publikationer

• 2014:50 Technical Note, A Study of Availability of Fuel Data for Sweden’s Spent Nuclear Fuel

  The study covers all types spent fuel planned to be placed in the final repository. It was carried out by selecting a sample of spent fuel and investigating the information available at the Nuclear Power Plants (NPP’s) in Sweden, the Central interim storage facility (Clab) and Studsvik. The results indicate that the required data is available and can be obtained for fuel unloaded after 1980.

  Innehållstyp: Publikationer