Filtered generated 216 hits.
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2015:10 SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects
Different lifecycle phases of a nuclear power plant present new human-technology- organization challenges to regulators and licensees. Organizational processes and practices that have evolved in one phase of development might be dysfunctional for the next phase, and the definition of “good safety culture” in practice might be unclear. The objective of the SafePhase study is to improve the...
Content type: Publications -
2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4
The analytical tools, which are fuel rod computer codes, that Quantum Technologies AB use and develop, contain models of several of the phenomena that are acting on the nuclear fuel (cladding temperature, fission gas driven pressure, strain and stress in the cladding, rod rupture, etc.) and how the separate effects interact in the complex integrated manner. The codes are under constant...
Content type: Publications -
2014:09 Further Development of the Core Simulator CORE SIM: Extension to coupled capabilities for BWRs
The developed tool is fully MatLab based and requires a set of input data from a commercial static core simulator. The driving perturbation can be specified both as a perturbation in thermo-hydraulic parameters or directly as a perturbation in macroscopic cross-sections. As output, the 3-dimensional spatial distribution of the noise in coolant density, pressure, enthalpy, inlet velocity, fuel...
Content type: Publications -
2015:09 PROSIR - Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel
Following an OCDE round robin proposal, 16 participants from 9 countries (USA, Japan, Korea (6 participants), Sweden, Germany, Czech Republic, Spain, EC and France (3 participants)) have been involved in a round robin study called PROSIR, Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel. The PROSIR project started already in 2003 and a final draft version of the main report...
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 -
2007:41 Dependency Analysis Guidence, Nordic/German Working Group on Common cause Failure analysis Phaase 1 project report: Comparison and application to test cases
The report “Nordic/German Working Group on Common cause Failure analysis. Phase 1 project report: Comparisons and application to test cases” presents a common attempt by the authorities and the utilities to create a methodology and experience base for defence and analysis of dependent failures. The performed benchmark application has shown that how the data is interpreted is of significant...
Content type: Publications -
2007:39 Influence of Crack Morphology on Leak Before Break Margins
The SKI regulation SKIFS 2004:2 allows for the use of Leak Before Break (LBB) as one way to provide assurance that adequate protection exists against the local dynamic consequences of a pipe break. The way to demonstrate that LBB prevails relies on a deterministic procedure for which a leakage crack is postulated in certain sections of the pipe based on the leak detection capability of the...
Content type: Publications -
2007:37 Identification of Common Cause Initiating Events Using the NEA IRS Database
The study carried out within the framework of this project is a continuation of work conducted for SKI in 1998 on the identification of Common Cause Initiators based on operational events documented in the NEA Incident Reporting System (IRS). This project covered the events reported in the IRS database with the incident date in the period of 1980- 01-01 – 2006-11-15. The events of highest...
Content type: Publications -
2007:24 Safety Management in Non-Nuclear Contexts Examples from Swedish Railway Regulatory and Company Perspectives
The authors describe important features of safety management and the results are modelled according to the systems perspective developed. These are definitions of safety management, the structure of the organizations, organizational change, regulatory and operational activities, safety strategy, threats to safety, information management and feedback, incident and accident reporting, and...
Content type: Publications -
2007:25 Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach
The study used the themes identified in an earlier study: definitions of safety management, the structure of the organizations, organizational change, regulatory and operational activities, safety strategy, threats to safety, information management and feedback, incident and accident reminders on different aspects of safety management in the nuclear context. reporting, and measurement of...
Content type: Publications