Filtered generated 755 hits.
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2015:32 Safe and responsible management of spent nuclear fuel and radioactive waste in Sweden - National Plan
The National Plan describes the general principles (national policies), the legislative, regulatory and organizational framework (national framework) as well as the strategies (national programme and systems) that control the safe and responsible management of spent nuclear fuel and of all types of radioactive waste in Sweden, now and in the future. Flavio Lanaro (project leader), Erica...
Content type: Publications -
2015:51 Technical Note, Initial State of Spent Nuclear Fuel
Sophie Grape, Carl Hellesen, Henrik Sjöstrand, Mattias Lantz, Staffan Jacobsson Svärd SSM English...
Content type: Publications -
2014:44 Technical Note, Independent evaluation of the number of critical canister positions in the KBS-3 repository at Forsmark – Main Review Phase
Independent calculations were carried out to estimate Ncrit, the number of canisters in critical positions that can be expected in the proposed repository at Forsmark, based on statistical simulations of SKB's geological discrete-fracture network (Geo-DFN) models, and taking into account SKB's full-perimeter criterion (FPC) and extended full-perimeter criterion (EFPC) to screen out...
Content type: Publications -
2014:46 Technical Note, QA in SKB’s Groundwater Flow Modelling
The general objective of the project is to provide review comments on SKB’s postclosure safety analysis, SR-Site, for the proposed repository at Forsmark. The specific objective is to get an understanding and an assessment of SKB’s quality assurance of the groundwater flow modelling in connection to SR-Site. The reliability of the results of the groundwater flow modelling depends inter alia...
Content type: Publications -
2013:37 Technical Note, Rock Mechanics – Evolution of fracture transmissivity within different scenarios in SR-Site – Main Review Phase
The current review assignment consists of a literature review and independent modeling for assessing the importance of fracture transmissivity change especially driven by shear loading due to SKB’s thermal, glacial and earthquake loading scenarios for the KBS-3 repository at Forsmark. In the first part of the report, SKB’s laboratory experiments on shear fracture dilation and extensive...
Content type: Publications -
2012:39 Technical Note, Review of Engineering Geology and Rock Engineering aspects of the construction of a KBS-3 repository at the Forsmark site – Initial Review Phase
In general, the reviewers find that the level of geomechanics data collected and synthesized to date has been impressive in scope and high in quality. The data collected has been incorporated into interlinked analyses concerning construction and operational performance of the repository. There are a number of uncertainties in the data and subsequent analyses that are unavoidable when dealing...
Content type: Publications -
2012:55 Technical Note, Review of SKB’s Radionuclide Transport Methodology
As part of SSM’s Initial Review Phase of SKB’s SR-Site safety assessment of the final disposal of spent nuclear fuel at the Forsmark site, Quintessa has been requested by SSM to consider whether SKB’s methodology to abstract FEPs (features, events, processes), as well as site information and other data, into assessment models for radionuclide transport is appropriate and sufficient for its...
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 -
2018:17 Assessment of structures subject to concrete pathologies (ASCET), phase 2
Background ASCET is an international research project initiated by WGIAGE1 OECD2 / NEA3. WGIAGE4 Concrete subgroup is a working group within the OECD / NEA whose task is to address issues concerning the maintenance of the integrity of concrete structures, proposals for general principles to optimally handle the challenges of integrity, especially with regard to aging of concrete structures.
Content type: Publications