Showing 3315 hits for ””
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2004:55 Development of an Input Model to MELCOR 1.8.5 for the Ringhals 3 PWR
Lars Nilsson SKI English ...
Content type: Publications -
02:08 Latency and Mode of Error Detection as Reflected in Swedish Licensee Event Reports
Ola Svenson, Ilkka Salo SKI English...
Content type: Publications -
02:29 Evaluation of the FRAPCON-3 Computer Code
Lars Olof Jernkvist, Ali Massih SKI English...
Content type: Publications -
01:51 Modelling of Ultrasonic Nondestructive Testing in Anisotropic Materials - Rectangular Crack
Anders Boström SKI English...
Content type: Publications -
01:42 Potential Effects of Organizational Uncertainty on Safety
Nancy E. Durbin, Anna Lekberg, Barbara D. Melber SKI English...
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 -
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 -
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 -
1995:19 Non-destructive Assay of Spent BWR Fuel with High-resolution Gamma-ray Spectroscopy
A method, based on high-resolution gamma-ray spectroscopy, has been developed for verification of burnup, cooling time, power history and, to some extent, the initial enrichment of spent BWR fuel. It is shown that, provided that the power history is known and corrected for, bumup and cooling time can be verified with accuracies within 3% and 60 days, respectively, for cooling times up to about...
Content type: Publications