Showing 3396 hits for ””
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02:39 Buffering Capacity of pH in Backfill
Steven Benbow, Peter Robinson, David Savage SKI English...
Content type: Publications -
2003:03 LJUNGSKILE 1.0
Christian Ekberg, Arvid Ödegaard-Jensen, Günter Meinrath SKI English...
Content type: Publications -
2016:25 Licensing of safety critical software for nuclear reactors
It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, ie the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors. An...
Content type: Publications -
2016:29 Evaluation of the Swedish participation in the Halden Reactor Project 2006–2014
This is a report on the evaluation of the Swedish participation in the Halden Reactor Project 2006-2014. The study has consisted in evaluating the types and extent of added value from the Swedish participation in the Halden Reactor Project, and to determine what additional added value the participation could supply for the Swedish authority. It can be concluded from the study that the impacts...
Content type: Publications -
2016:39 Recommended residual stress profiles for stainless steel pipe welds
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to analyze stainless steel pipe welds to obtain good estimations of weld residual stress (WRS) distributions. Detailed knowledge of the residual stress field in different types of welds is important since they can have substantial influence on...
Content type: Publications -
2016:27 Validation of fatigue fracture mechanics approaches
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 evaluate fatigue flaw tolerance assessments used in industry, which are based on the fracture mechanical approach implemented in ProSACC. Objective The present study aims to validate the used...
Content type: Publications -
1990:18 Some Estimates of the Total NuclideInventory in the Year 2100 from Swedish Nuclear Power Production
The total nuclide inventory in spent fuel from the swedish nuclear power programme has been estimated for three cases. All reactors were arrumed to operate until the year 2010 and then shut down simultaneously. All fuel used was assumed to be based on enriched natural uranium. The reactors were assumed to shut down after 25 years of commercial operation, but not later than in the year 2010.
Content type: Publications -
91:12 Radionuclide Migration within Fractured Rock: The Impact of Colloids upon Geosphere Calculations
P. Grindrod SKI English...
Content type: Publications -
93:06 CRACKER A Program Coupling Chemistry and Transport, Version 92-11
A. Emrén SKI English...
Content type: Publications -
2006:24 Crack Characterisation for In-service Inspection Planning An Update
The need to qualify non-destructive testing systems (NDT systems) for pre- and in-service inspection has been recognised to a greater or lesser extent for many years in many countries engaged in nuclear power generation. However, NDT in general and qualification of NDT systems in particular are multidisciplinary and complex tasks. Development of NDT systems and demonstration of their...
Content type: Publications