Filtered generated 399 hits.
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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 -
2013:29 Regulatory Approaches in Nuclear Power Supervision
The objective of this follow-up study was to support SSM in further understanding regulatory approaches and how they can be combined as part of effective strategies. The survey was intended to assist SSM in identifying current standards, experiences, and practices in the regulation of nuclear power plants. The results will also be valuable for the participating authorities as well as other...
Content type: Publications -
2008:30 A model for fission gas release from mixed oxide nuclear fuel
Nuclear fuel containing mixed oxide (MOX) pellets have been used since the 1960´s. MOX fuel pellets are made from a mixture of uranium and plutonium oxide. MOX allows the large quantities of fissile isotopes produced and remaining in spent nuclear fuel from light water reactors to be recycled. Producing MOX fuel can be seen as a method to more efficiently use the natural uranium since...
Content type: Publications -
2011:13 Investigation of Discrete-Fracture Network Conceptual Model Uncertainty at Forsmark
Flow modelling using alternative assumptions regarding conceptual and parametric uncertainty in the spatial and structural relationships among fractures indicates elevated flow rates and groundwater velocities to deposition holes compared to SKB’s flow modelling results. Simulated sampling of fractures in boreholes does not indicate any reason to exclude the proposed spatial and structural...
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 -
2007:05 Development of an Input Model to MELCOR 1.8.5 for Oskarshamn 3 BWR
200 Lars Nilsson SKI English...
Content type: Publications -
2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository
PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...
Content type: Publications -
2007:07 Inquiry into the radiological consequences of power uprates at light-water rectors worldwide
In Sweden, most of the nuclear power plants are planning power uprates within the next few years. The Department of Occupational and Medical Exposures at the Swedish Radiation Protection Agency, SSI, has initiated a research project to investigate the radiological implications of power uprates on light-water reactors throughout the world. The project was divided into three tasks: A compilation...
Content type: Publications -
2008:09 The Generalised Ecosystem Modelling Approach in radiological assessment
An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments,...
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