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Din avgränsning ger 186 träffar.

• 2012:35 Technical Note, Review of SKB’s Code Documentation and QA for the SR-Site Safety Assessment

  This initial review examined the Swedish Nuclear Fuel and Waste Management Company (SKB) code documentation and quality assurance, which is important to the safety assessment SR-Site because the computer codes used must be both suitable for the analyses performed and capable of producing accurate results for those analyses. SKB has prepared a report that summarizes the code documentation...

  Innehållstyp: Publikationer

• 2012:43 Technical Note, Literature review of groundwater flow in permafrost

  The Swedish Radiation Safety Authority (SSM) assigned the task of compiling the state of the knowledge with respect to groundwater flow in permafrost conditions. In particular, the study was to consider whether (i) the main processes related to groundwater flow in permafrost were understood, (ii) appropriate field data was available, and (iii) current models appropriately represent the...

  Innehållstyp: Publikationer

• 2012:46 Technical Note, Review of Landscape Models used in SR-Site

  As part of SSM’s Initial Review phase of SKB’s SR-Site safety assessment for the proposed final disposal of spent nuclear fuel at the Forsmark site, Quintessa was given the assignment to consider whether the landscape models and supporting data utilised by SKB are appropriate and fit for purpose. This Technical Note summarises the findings of Quintessa’s review. SKB’s approach to the...

  Innehållstyp: Publikationer

• 2012:49 Hydrogeological characteristics of sites for low- and intermediate-level waste disposal

  The Forsmark area with its selected two sites and the Laxemar-Simpevarp area with its two sites are broadly similar in terms of lithology, rock ages, and tectonic histories. The two areas differ in terms of degree of deformation, and tectonic fabric. Some lithologic and tectonic differences are noticeable between the two sites in the Forsmark area and between the two sites in the...

  Innehållstyp: Publikationer

• 2012:48 Technical Note, Use of Solubility Limits in the SR-Site Safety Assessment

  In a radioactive waste disposal environment, in some potential situations (scenarios) a disposed canister containing spent fuel may be breached and the fuel may come into contact with groundwater. The concentration of a radioactive element such as uranium may rise to a level where the solution is saturated. No more of the radioactive element may dissolve and a precipitated solid may be formed.

  Innehållstyp: Publikationer

• 2012:42 Technical Note, Initial review of physical properties and processes of the buffer and backfill – Installation and initial state

  The technical note briefly summarises the proposed designs and functions of the buffer and backfill, and examines SKB’s progress in manufacturing, installing and testing its proposed solutions. In brief, the review suggests that there are some procedural and practical engineering aspects (e.g., quality assurance procedures, backfilling rates) and several physical processes to do with the...

  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

• 2015:22 Technical Note, Further modelling and sensitivity study using the GEMA-Site “alternative biosphere models” and review of material from SKB’s RFI response

  Denna rapport har upprättats som en del av SSM:s huvudgranskning av SKB:s säkerhetsanalys av den långsiktiga säkerheten för KBS-3 (SR-Site), en geologisk slutförvarsanläggning, som SKB planerar uppföra i Forsmark. Granskningen tar upp de metoder som används för dosberäkningar i SR-Site, speciellt vad gäller transporter, ackumulering och...

  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