Filtered generated 375 hits.
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2012:03 The IAEA Integrated Regulatory Review Service Mission to Sweden in February 2012
The Swedish Government decided on January 22, 2009 to mandate the Swedish Radiation Safety Authority, SSM, to apply for an international review of the Author-ity and its areas of supervision, an ‘IRRS’ (Integrated Regulatory Review Service) carried out by the International Atomic Energy Agency (IAEA). On February 25, 2009, SSM made a formal request to the IAEA for an IRRS in Sweden. The time...
Content type: Publications -
2011:33 Mathematical modelling of ultrasonic testing of components with defects close to a non-planar surface
The report describes work that has been performed in order to model ultrasonic testing of components that contain a defect close to a non-planar surface. The studies have been performed in both 2D and 3D, and in 2D in both the anti-plane (SH) and the in-plane (P-SV). The results show that the presence of a non-planar back wall can reduce the detectability of defects close to the surface. The...
Content type: Publications -
SKI Report 2008:01 Reliability Data for piping Components in Nordic Nuclear Poer Plants "R-Book" Project Phase 1
SKI Report 2008:01 - “Reliability Data for Piping Components in Nordic Nuclear Power Plants - R-Book Project Phase I” – is a planning document for a new R&D project to develop a piping component reliability parameter handbook for use in probabilistic safety assessment (PSA) and related activities. Included in this handbook will be pipe leak failure rates and rupture frequencies that are...
Content type: Publications -
2008:38 Methodology for description and evaluation of cost profiles and cost structure during transitions period
A demanding task for our generation is to assure the appropriate financial resources are invested in the Swedish Nuclear Waste Fund. This will enable future generations to execute the decommissioning and dismantling of nuclear power reactors and other nuclear facilities in a prudent manner. The main aim is to fulfil the demands of environmental and health codes in a pan-European context...
Content type: Publications -
2009:07 Dependency Analysis Guidance Nordic/German Working Group on Common Cause Failure analysis
The Regulatory Code SSMFS 2008:1 of Swedish Radiation Safety Authority (SSM) includes requirements regarding the performance of probabilistic safety assessments (PSA), as well as PSA activities in general. Therefore, the follow-up of these activities is part of the inspection tasks of SSM. According to the SSMFS 2008:1, the safety analyses shall be based on a systematic identification and...
Content type: Publications -
2008:50 Study on Developments in Accident Investigation Methods: A Survey of the “State-of-the-Art”
The objective of this project was to survey the main accident investigation methods that have been developed since the early or mid-1990s. The motivation was the increasing frequency of accidents that defy explanations in simple terms, for instance cause-effect chains or “human error”. Whereas the complexity of socio-technical systems is steadily growing across all industrial domains,...
Content type: Publications -
2009:05 Survey on requirements for independent reviews and inspections of electrical and I&C equipment
This survey is a first step to support the work to develop the Swedish regulations in the area of independent review and inspection in the process supporting implementation of electrical equipment in nuclear power plants. The report consists of a summary of different regulations in the area and also an analysis of the differences between the electrical and mechanical field especially in the...
Content type: Publications -
2008:29e Safety and Radiation Protection at Swedish Nuclear Power Plants 2007
The safety level of the plants is maintained at an acceptable level. SKI has in its regulatory supervision not found any known deficiencies in the barriers which could result in release of radioactive substances in excess of the permitted levels. SKI considers that improvements have been implemented during the year in the management, control and following up of safety work at the plants. In...
Content type: Publications -
2007:15 Evaluation of the FRAPTRAN -1.3 Computer Cod
The FRAPTRAN-1.3 computer code has been evaluated regarding its applicability, modelling capability, user friendliness, source code structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under reactor power and coolant transients, such as overpower transients, reactivity initiated accidents (RIA),...
Content type: Publications -
2007:06 Probabilistic Safety Goals - Phase 1 -Status and Experiences in Sweden and Finland
Based on a series of interviews and on literature reviews as well as on a limited interna- tional over-view, the project has described the history and current status of safety goals in Sweden and Finland. A number of issues were discussed more in detail, including the status of the safety goals in view of the fact that they are often exceeded, strategies for handling violations of safety...
Content type: Publications