Filtered generated 80 hits.
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2010:31 Buffer erosion: An overview of concepts and potential safety consequences
In its safety analysis SR-Can, SKB reported preliminary results and conclusions on the mechanisms of bentonite colloid formation and stability, with a rough estimate of the consequences of loss of bentonite buffer by erosion. With the review of SR-Can the authorities (SKI and SSI) commented that erosion of the buffer had the greatest safety significance, that the understanding of the...
Content type: Publications -
2010:09 Copper Thermodynamics in the Repository Environment up to 130˚C
The mechanisms of copper corrosion for a KBS-3 repository for spent nuclear fuel need to be known with a high level of confidence. This is because the overall rate of copper canister corrosion (accounting for corroding species concentrations, geochemical conditions and the mass transport through surrounding barriers) provides an essential performance indicator in safety assessment. A...
Content type: Publications -
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...
Content type: Publications -
2011:09 Is Copper Immune to Corrosion When in Contact With Water and Aqueous Solutions?
The KBS-3concept implies that spent nuclear fuel is placed in copper canisters surrounded by clay and finally placed approximately 500 m down from surface into granitic bedrock, in order to isolate the spent nuclear fuel from humans and environment for very long time scales (i.e. millions of years). The concept is based on the multi-barrier principle, in this respect the barriers are the...
Content type: Publications -
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...
Content type: Publications -
2009:33 Workshop on spent fuel performance, radionuclide chemistry and geosphere transport parameters, Lidingö 2008: Overview and evaluation of recent SKB procedures
The safety assessment for disposal of spent nuclear fuel canister in the Swedish bedrock should thoroughly address the time period after a containment failure. Such a failure could be expected as a result of corrosion damage or mechanical failure due to rock movement. This report mainly covers some issues connected to parameters used for radionuclide transport calculations in the areas of...
Content type: Publications -
2010:05 Discrete-Feature Model Implementation of SDM-Site Forsmark
SSM has been following the investigations of the two candidate sites for a repository for spent nuclear fuel that the Swedish Nuclear Fuel and Waste Management Company (SKB) have been undertaking. SKB has reported the results of the investigations as site descriptive models. These models will be used to underpin the safety analysis following the license application of the repository planned...
Content type: Publications -
2009:35 Evaluation of SKB/Posiva’s report on the horizontal alternative of the KBS-3 method
The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. The method has two design alternatives: the vertical (KBS-3V) and the horizontal (KBS-3H). SKB and Posiva have conducted a joint research, development and demonstration (RD&D) programme in 2002-2007 with the overall aim of establishing whether the KBS-3H represents a...
Content type: Publications -
2010:25 Modelling Coupled Processes in the Evolution of Repository Engineered Barrier Systems using QPAC-EBS
Currently in Sweden, the SR-Site safety assessment for a spent nuclear fuel repository is being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB). The planned SSM review of this work requires access to a sufficient modelling capability to assess the combined performance of the engineered barriers (spent fuel canister, buffer and backfill) and the natural geosphere...
Content type: Publications -
2010:24 On Cost Estimate for Decommissioning of one Isotope Central
The present generation has the responsibility to ensure and guarantee that sufficient financial resources are accrued into the Swedish Nuclear Waste Fund to cover all future costs. Thus, the next generation, as well as any succeeding generations, will have the financial resources required in order to undertake the necessary measures, in an appropriate manner, for the decommissioning and...
Content type: Publications