Search

Filtered generated 761 hits.

Sort on:

Relevance Date
  • 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
  • 2015:43 Robust structural verification of pressurized nuclear components subjected to ratcheting

    Background Pressurized components in nuclear applications that are subjected to cyclic loading may exhibit progressive deformation, so called structural ratcheting. If the component is made out of a material that are deformation hardening, it may also exhibit material ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material...

    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
  • 2010:07 Indicators of safety culture – selection and utilization of leading safety performance indicators

    Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report explains the distinction between lead and lag indicators and proposes a framework of three types of...

    Content type: Publications
  • 2010:36 Guidance for the Definition and Application of Probabilistic Safety Criteria

    Safety goals are defined in different ways in different countries and also used differently. Many countries are presently developing them in connection to the transfer to risk-informed regulation of both operating nuclear power plants (NPP) and new designs. However, it is far from self-evident how probabilistic safety criteria should be defined and used. On one hand, experience indicates that...

    Content type: Publications
  • 2010:22 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 16

    This report constitutes Stage 16 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Results up to Stage 15 were reported in SKI and SSM reports, as listed below and in the Summary. The results have also been published in international journals and have been included in both licentiate- and doctor’s degrees.

    Content type: Publications
  • 2010:45 Evaluation of models for cyclic plastic deformation – A literature study

    Analysis of nuclear components subjected to cyclic plastic deformation is normally based on the American standard ASME III. With the focus to improve the modeling of the stress-strain response under non-monotonic loading, several models for the analysis of cyclic plastic deformation have been developed in recent years. However, experience shows that the analysis and evaluation of plastic...

    Content type: Publications
  • 2009:04 Radon in DWELLINGS in the Republic of Kalmykia. Results from the National Radon Survey 2006-2007

    The National Radon Survey in the Republic of Kalmykia, Russian Federation during 2006 – 2007 was carried out in a cooperation project between the Swedish Radiation Protection Authority (SSI) and the Russian Institute of Radiation Hygiene (RIRH). This work was financed by the Russian Institute of Radiation Hygiene and the Swedish Agency for Development Cooperation (SIDA). In August 2006 SSI,...

    Content type: Publications