Filtered generated 403 hits.
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2011:26 The influence of temperature and fluid pressure on the fracture network evolution around deposition holes of a KBS-3V concept at Forsmark, Sweden
In preparation for the review of SKB’s license application for disposal of spent nuclear fuel, SSM is conducting studies to evaluate the performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at about 500 m depth and embedded in clay. Thus, the rock, the clay and the copper canister...
Content type: Publications -
2012:11 Issues in the corrosion of copper in a Swedish high level nuclear waste repository
The objective with this research project was to increase knowledge in the area of copper corrosion in the planned repository environment and obtain information on how copper corrosion evolves during the assessment period of 100 000 years. The equilibrium chemical composition of groundwater close to the canister as a function of temperature has been calculated by use of a thermodynamics code...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications -
2019:17 ENSREG 1st Topical Peer Review – Ageing Management, Swedish National Action Plan
SSM perspective Background The European Union’s Nuclear Safety Directive 2014/87/EURATOM (NSD) requires the member states to undertake topical peer reviews (TPR) every 6 years with the first starting in 2017. The member states, acting through the European Nuclear Safety Regulators Group (ENSREG), have decided that the topic for the first topical peer review is ageing management. This report...
Content type: Publications -
2018:15 Review of Geochemical Data Utilisation in SR-Site Safety Assessment
The objective of this study is to understand how data for groundwater compositions were used in producing the Site Descriptive Model for Forsmark and as input data for the safety assessment, SRSite. Improving this understanding sheds further light on the significance of data uncertainties, data processing and interpretation on the degree of uniqueness in the descriptive model, parameterisation...
Content type: Publications -
2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities
Background Many practices involving radioactive substances generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions from a radiation protection point of view. According to regulations issued by the SSM, such decisions must be based on...
Content type: Publications -
2009:30 A Review of Evidence for Corrosion of Copper by water
The planned spent nuclear fuel repository in Sweden relies on a copper cast iron canister as the primary engineered barrier. The corrosion behaviour of copper in the expected environment needs to be thoroughly understood as a basis for the post-closure safety analysis. It has been shown that corrosion may indeed be the primary canister degradation process during the utilised assessment period...
Content type: Publications -
2009:22 Alternative modelling of brittle structures in a sub-area of the SKB candidate area at Forsmark, eastern Sweden
A reasonable understanding of the character of the bedrock hosting a deep geological repository, i.e. the natural barrier, is an important component in the safety assessment of the deep geological repository for spent nuclear fuel. The structures in the rock, together with the regional stress field, affect the mechanical stability of the bedrock and the ground water transport within the...
Content type: Publications -
2008:48E Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Co´s (SKB) RD&D Programme 2007
The review of the RD&D Programmes (Research, Development, Demonstration) prepared by the Swedish Nuclear Fuel and Waste Management Co (SKB) is a recurrent task that the Swedish Nuclear Power Inspectorate (SKI) must carry out as a regulatory authority with the support of reviewing bodies of which the most important is the Swedish Radiation Protection Authority (SSI). The review statement for...
Content type: Publications