Filtered generated 375 hits.
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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 -
2012:28 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill – Geochemical processes
This report consists of a Technical Note in SSM’s initial review phase of SKB’s safety analysis SR-Site. The aim of the initial review of issues concerning geochemical processes in buffer and backfill in a final repository is to make a broad illustration and review of SR-Site together with its subordinate references, as well as to identify potential needs for complementary information or...
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 -
2018:15 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 -
2018:17 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 -
2018:18 Procedure for Safety Assessment of Components with Defects
Background SSM and the Swedish nuclear power plant owners have financed Kiwa Inspecta Technology in Sweden to develop a new version of the handbook for assessment of defects. This represents a major update of the former fracture mechanics handbook that was published at SSM as Research 2008:01. The procedure in the handbook is based on the British R6-method where the failure mechanisms...
Content type: Publications -
2018:24 Structural equation modelling for analysis of human and organizational factors in nuclear power plant control rooms
SSM perspective Background During the supervisory work of the Swedish Radiation Safety Authority (SSM), a need was identified to develop the methods used when evaluating control room work in the central control rooms of nuclear power plants. Benchmarking is commonly used today, with reference values from earlier Integrated System Validation (ISV), when ISV is available. Often, ISV performs...
Content type: Publications -
2016:28 Fatigue fracture surface characterization and investigation
Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to examine the obtained fatigue cracks with an optical microscope. Objective The present study performs a fractographical examination of the obtained fatigue cracks with the aim of determine where...
Content type: Publications