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  • 2014:20 An evaluation of high-temperature creep of zirconium alloys: data versus models

    In this report Dr Massih presents correlations for creep in different phases of zirconium alloys and also presents a general solution to the difficulty of accurately describing the material properties in phase transition for several zirconium alloys. Based upon superplasticity relations, models are adapted to fit with experimental data for materials in transition regions. The creep models are...

    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
  • 2011:22 Infiltration of dilute groundwaters and resulting groundwater compositions at repository depth

    The planned Swedish concept for final disposal of spent nuclear fuel includes copper canisters placed in deposition holes at about 500 m depth in granitic bedrock. The copper canisters will be surrounded by bentonite buffer with the objective of inhibiting groundwater flow adjacent to the canister. It has been discovered that dilute glacial melt-water may induce erosion of the buffer material.

    Innehållstyp: Publikationer
  • 2012:21 Technical Note, Initial Review Phase for SKBs Safety Assessment SR-Site: Corrosion of Copper

    The uniform and localized corrosion treatments as well as stress corrosion cracking positions currently considered by SKB have been examined with the objective of identifying key unresolved issues or gaps, needs and opportunities. In conjunction with the review of the SKB reports listed in Appendix 1, there has been some consideration of the broader literature. This summary highlights the...

    Innehållstyp: Publikationer
  • 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
  • 2011:21 Workshop on spent fuel performance and radionuclide chemistry -Rånäs 2010: Assessment of some outstanding issues

    The safety assessment for final disposal of spent nuclear fuel has to comprehensively address the stage when containment barriers have failed and when radionuclide releases occur to the surrounding groundwater at repository depth. Essential processes for estimating risk/dose related to this scenario involve the release of radionuclide from the spent fuel surfaces due to radio-lytic oxidative...

    Innehållstyp: Publikationer
  • 2013:36 Technical Note, Review and assessment of aspects of the Qeq concept – Main Review Phase

    This technical review assignment considers the models and abstractions that Swedish Nuclear Fuel and Waste Management Company (SKB) developed to represent transport of dissolved constituents in the near field at the Forsmark site, in particular the Qeq abstraction for diffusive transport. SKB uses the Qeq parameter to scale concentration gradients in order to estimate dissolved-species fluxes...

    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
  • 2012:17 Technical Note, Corrosion of copper canister

    It is expected that the inflow of ground water to the deposition holes and tunnels in the Forsmark repository will be very slow. Thus, it might take some few hundred years up to thousand years before the deposition holes are filled with ground water and it might take 6000 years or more before the bentonite buffer is fully water saturated and pressurized. The copper canisters will therefore...

    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