Filtered generated 377 hits.
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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 -
2016:29 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 -
2015:07 TEM-lamella lift-out from the crack tip region of Alloy 600 for high resolution electron microscopy examination
This report contributes to the development of a method for high-quality TEM lamella preparation from crack tip regions of nuclear materials. A standard compact tension (CT) specimen of Alloy 600 previously tested for stress corrosion crack growth in simulated PWR primary water was used to demonstrate the benefit of the proposed method. This report describes the procedure for cutting the CT...
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 -
2020:13 Core data Research at Uppsala University
SSM perspective Background This project is to support a research group at Uppsala University in the research field of nuclear data for applications. Nuclear data research is about measuring microscopic cross-sections and developing theoretical nuclear models to create evaluated nuclear data libraries. These nuclear data libraries are used in different applications such as, nuclear technology,...
Content type: Publications -
1994:15 Aging Degradation of Concrete Structures in Nuclear Power Plants
This report on the aging-related degradation of concrete structures in nuclear power plants was prepared by Battelle Seattle Research Center for the Swedish Nuclear Power Inspectorate (SKI). The purpose of this report is to provide an understanding of how concrete structures in nuclear power plants degrade over time. This report is based on the studies of concrete aging commissioned by the...
Content type: Publications -
1994:14 Evaluation of acceptance criteriafor data on environmentally assistedcracking in light water reactors
The assessment of possible sub-critical crack growth through environmentally assisted cracking (EAC) is a commonly encountered problem in safety evaluations of light water reactor components. The numerous factors influencing EAC fall into three main groups (material, medium and loading), but their interactions are highly complex. Field assessments usually rely on the evaluation of...
Content type: Publications -
1992:3 Characterization of seismic ground motions for probabilistic safety analyses of nuclear facilities in Sweden. SUMMARY REPORT
In Scandinavia seismic activity is generally low. Only a few incidents have been registered in historic time, which might have damaged an industrial plant of today. The risk of a nuclear accident in Sweden, caused by an earthquake, may thus be considered to be low. The two latest reactors Forsmark 3 and Oskarshamn 3 have been analysed and designed to resist a specified earthquake. For the...
Content type: Publications