Filtered generated 375 hits.
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2007:10 DECOVALEX-THMC - Task D
The DECOVALEX project is an international cooperative project initiated by SKI, the Swedish Nuclear Power Inspectorate, with participation of about 10 international organizations. The name DECOVALEX stands for DEvelopment of COupled models and their VALidation against Experiments. The general goal of this project is to encourage multidisciplinary interactive and cooperative research on...
Content type: Publications -
In case of an alarm from Forsmark's nuclear power plant – What you need to know
SSM English...
Content type: Publications -
Fitness for work certificate – Work involving ionising radiation
You need Adobe Acrobat Reader in order to read and fill out PDF forms. SSM Svenska You need Adobe Acrobat Reader in order to read and fill out PDF forms.
Content type: Publications -
1997:05 SKI SITE-94
The Swedish Industry program for deep geological disposal of spent nuclear fuel and high-level radioactive waste is now in the early stages of the site selection process, with feasibility studies underway in 5 to 10 municipalities. According to the Swedish Nuclear Fuel and Waste Management Co., SKB (SKB RD&D Programme, 1995), the ongoing siting process involves selection of two sites for...
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 -
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 -
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 -
2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents
Ali R. Massih, Lars Olof Jernkvist SSM English...
Content type: Publications