Din avgränsning ger 571 träffar.
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2011:12 Analysis of Barrier Performance: Modelling of Copper corrosion scenarios with and without buffer erosion
The purpose of this project was to develop a numerical modelling capacity to address the corrosion of the copper canister under gradually changing transport conditions caused by buffer erosion and removal of buffer mass. Due to the complexity of this task, such a model cannot be realistic in all respects, but the present effort should address the feasibility of solving numerical and...
Innehållstyp: Publikationer -
2011:11 Handling Interfaces and Time-varying Properties in Radionuclide Transport Models
Quintessa’s QPAC code has been used to investigate the Qeq approach. The conclusions from this simulation study are the following. The basic approach to calculating Qeq values is sound, however, narrow channels could lead to the same release as larger fractures with the same pore velocity, so a channel enhancement factor of √10 should be considered. A spalling zone that increases the area of...
Innehållstyp: Publikationer -
2012:08 Deterministic Assessment of Future Costs for Dismantling (FA)
In this study a model for advanced deterministic cost calculation has been used to find a parametric value on the cost for dismantling of the FA-facility. The study gives good description of good practise to collect, test and utilise input data in a systematic way in order to make prudent cost estimates for any particular nuclear installation The Swedish Law stipulates that future expenses...
Innehållstyp: Publikationer -
2012:15 Technical Note, A review of the mechanical integrity of the canister
An introductory review of SR-Site has been conducted with respect to the mechanical integrity of the canister. The review is focused on the copper canister and the nodular cast iron insert. Review results show that a number of loads and loading scenarios for the copper canister has not been analysed by SKB. The importance of sufficient creep ductility of the copper material and sufficient...
Innehållstyp: Publikationer -
2012:25 Workshop on Seismology
This report summarizes the issues discussed at the workshop and extracts the essential viewpoints that have been expressed. The report is not to consider as a comprehensive record of all the discussions at the workshop and individual statements made by workshop participants should be regarded as opinions rather than proven facts. This report includes, apart from the workshop synthesis, the...
Innehållstyp: Publikationer -
2018:26 Reaktorinneslutningarnas respons vid höga inre tryck och reducerad förspänning
I föreliggande studie har det genom numerisk modellering undersökts huruvida tillämpning av alternativ B enligt Regulatory Guide 1.90 (R.G. 1.90) är ett tillförlitligt sätt att bedöma reaktorinneslutningens integritet. Vid genomförandet har två olika numeriska modeller använts, en global 3D-modell respektive en ringmodell. Resultaten pekar på...
Innehållstyp: Publikationer -
2008:11 Discrete-Feature Modelling of Groundwater Flow and Solute Transport for SR-Can Review
Review External review contribution in support of SKI's and SSI's review of SR-Can. The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for...
Innehållstyp: Publikationer -
2008:08 Review of SKB:s Work on Coupled THM Processes Within SR-Can External review contribution in support of SKI:s and SSI:s
The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear fuel in Sweden 2010. In support of this application SKB will present a safety...
Innehållstyp: Publikationer -
2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister
The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration...
Innehållstyp: Publikationer -
2007:08 DECOVALEX-THMC - Task B
This report summarizes the work contributed to Phase 2 of Task B of the international DECOVALEX-THMC project, which took place during the period of March 2004 to May 2006. The Phase 2 work incorporated the use of a wide range of numerical models to simulate the failure of a number of intact rock core samples, from the APSE tunnel at Äspö HRL, as tested in uniaxial compression and other...
Innehållstyp: Publikationer