Filtered generated 296 hits.
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1995:19 Non-destructive Assay of Spent BWR Fuel with High-resolution Gamma-ray Spectroscopy
A method, based on high-resolution gamma-ray spectroscopy, has been developed for verification of burnup, cooling time, power history and, to some extent, the initial enrichment of spent BWR fuel. It is shown that, provided that the power history is known and corrected for, bumup and cooling time can be verified with accuracies within 3% and 60 days, respectively, for cooling times up to about...
Content type: Publications -
2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository
Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish...
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 -
2011:08 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...
Content type: Publications -
2007:03 Variability and Uncertainties of Key Hydrochemical Parameters for SKB Sites
An important part of the site investigations conducted by the Swedish Nuclear Fuel and Waste Management Company (SKB) is the characterisation of groundwater chemical conditions in the deep bedrock environment where a final repository for spent nuclear fuel is planned to be located. This work is currently in its final stages at the two candidate sites, Forsmark and Laxemar, and should be...
Content type: Publications -
2007:02 Stakeholder involvement in Swedish nuclear waste management
This report have attempted to show the development of stakeholder involvement in the siting of a final repository for Sweden’s spent nuclear fuel as resembling something other than a straightforward linear process of improvement and refinement. Stakeholder involvement has developed, over the past 15 years or so, in something more like a patchwork of different shapes and forms. Some of the...
Content type: Publications -
2007:32 Low pH Cements
Concrete and cement are used in constructions as well as in conditioning of waste in repositories for radioactive waste. The development of low pH cements for use in geological repositories for radioactive waste stem from concerns over the potential for deleterious effects upon the host rock and other EBS materials (notably bentonite) under the hyperalkaline conditions (pH > 12) of cement...
Content type: Publications -
2007:21 On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden
Marek Vasko, Vladimir Daniska, Frantisek Ondra, Peter Bezak, Kristina Kristofova, Peter Tatransky, Matej Zachar, Staffan Lindskog SKI English...
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 -
2018:01 Monte Carlo patient-specific pre-treatment QA system for volumetric modulated arc therapy
Background According to the Swedish Radiation Safety Authority's Regulations in Radiotherapy (SSMFS 2008:33) are Swedish clinics required to verify the individual dose to patients, prior the first time a new treatment is given. To fulfil this requirement, current clinics perform in-vivo dosimetry in three dimensional conformal radiation therapy (3DCRT), which means that the entrance of...
Content type: Publications