Filtered generated 755 hits.
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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 -
2012:25 Workshop on Seismology
This report summarizes the issues discussed at the workshop and extracts the essential viewpoints that have been expressed. The report is not to consider as a comprehensive record of all the discussions at the workshop and individual statements made by workshop participants should be regarded as opinions rather than proven facts. This report includes, apart from the workshop synthesis, the...
Content type: Publications -
1991:08 The Potential Significance of Permafrost tothe Behaviour of a Deep RadioactiveWaste Repository
Permafrost is one of the scenarios that is being considered as part of the groundwater flow and transport modelling for the Project-90 assessment. It is included as one of the primary Features, Events and Processes (FEPs) which are being kept outside the PROCESS SYSTEM in the SKBjSKI scenario development project (Andersson at aI, 1989). There is a large amount of evidence that Sweden has...
Content type: Publications -
2014:28 Numerical simulation of ductile crack growth in residual stress fields
The study has shown on the capability of the cell model in capturing the effects on ductile tearing from limited pre-load levels and a residual stress field. Some of the conclusions are as follows: No distinctive influence on the material fracture toughness is observed from pre-loading (work hardening), both tensile and compressive, at room temperature of 1.5 or 3 % total strain. The cell...
Content type: Publications -
2016:31 Measures and method characteristics for early evaluation of safe operation in nuclear power plant control room systems
The Swedish Radiation Safety Authority’s (SSM) experience is that there is a need to develop evaluation methods in parallel with the development of control rooms in conjunction with construction modifications and other changes. This includes more indepth analysis of the methods used today. Another aspect is that conventional methods of evaluating control rooms and issues need to be...
Content type: Publications -
2015:10 SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects
Different lifecycle phases of a nuclear power plant present new human-technology- organization challenges to regulators and licensees. Organizational processes and practices that have evolved in one phase of development might be dysfunctional for the next phase, and the definition of “good safety culture” in practice might be unclear. The objective of the SafePhase study is to improve the...
Content type: Publications -
2015:20 The effects of mild, acute hypoxia on cognitive performance
Room air with reduced oxygen levels that prevent materials to ignite and combust is a cost-effective and increasingly popular fire prevention method. For system safety reasons, the effects of hypoxia, that is, the lack of sufficient oxygen (that is, less than 21% oxygen which is the approximate oxygen level of normal air), on cognitive performance of persons working under such conditions are...
Content type: Publications -
2001:33 Sweden and the Bomb. The Swedish Plans to Acquire Nuclear Weapons, 19451972
Dr Thomas Jonter, Uppsala University, Department of History, S:t Larsgatan 2, SE-753 10 Uppsala, Sweden. September 2001 SKI English...
Content type: Publications -
91:18 The CALIBRE Source-Term Code: Technical Documentation for Project-90
P. Robinson, K. Worgan SKI English...
Content type: Publications -
2012:50 Fatigue Margins for Austenitic Stainless Steels in ASME Boiler and Pressure Vessel Code – A Literature Study
Knowledge about the margins against fatigue failure in nuclear piping systems is essential. Therefore, the margins in the ASME Boiler and Pressure Vessel Code (section III) fatigue design procedure for austenitic steels, type 304/316, as applied to real components have been investigated in this literature study. It is concluded that the current knowledge about the margins in ASME for...
Content type: Publications