Din avgränsning ger 427 träffar.
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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...
Innehållstyp: Publikationer -
2010:18 Radionuclide Transport: Preparation During 2009 for the SR-Site Review
Post-closure safety assessments for nuclear waste repositories involve radioecological modelling for an underground source term. Following several decades of research and development, the Swedish Nuclear Waste Management Company (SKB) is approaching a phase of license application. According to SKB’s plans, an application to construct a geological repository will be submitted by the end of...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
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...
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 -
2011:08 Workshop on Copper Corrosion and Buffer Erosion Stockholm 15-17 September 2010
In SSM:s preparation for reviewing SKB:s license application for disposal of spent nuclear fuel, a series of technical workshops have been conducted. The main purpose of this type of workshops is to get an overall understanding of the state of knowledge on interdisciplinary issues as well as of questions in the research front by inviting several experts. Previous workshops have addressed the...
Innehållstyp: Publikationer -
2011:03 On Decommissioning Cost for Nuclear Power Plants
This research report summarizes what has changed over the latest 15 years concerning actual and estimated costs for the D&D of nuclear power plants that have been shut down permanently. It also reports on the availability of detailed information for actual nuclear power plant D&D cost breakdowns. The results will be one supporting document in the review of the estimates submitted for...
Innehållstyp: Publikationer -
2007:09 DECOVALEX-THMC - Task C
This report describes the results of Task C1 of the international DECOVALEX– THMC project devoted to Excavation Damage Zone (EDZ) in argillaceous rock at the Tournemire site in France. Task C of the project is aimed to understand the physical phenomena induced by excavation in the argillaceous rock. The task is to develop adequate numerical models for interpretation of observed damaged zones...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer