European clearinghouse on nuclear power plants operational experience feedback
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V. Ranguelova
Abstract
Learning from operational experience and applying this knowledge promptly and intelligently is one of the ways to improve the safety of Nuclear Power Plant (NPP). Recent reviews of the effectiveness of Operational Experience Feedback (OEF) systems have pointed to the need for further improvement, with importance being placed on tailoring the information to the needs of the regulators. In 2007, at the request of a number of nuclear safety regulatory authorities in Europe, the Institute for Energy of the European Commission's Joint Research Centre (EC JRC) initiated a project on Nuclear Power Plant operational experience feedback, which adopts an integrated approach to the research needed to strengthen the European capabilities for assessment of NPP operational events and to promote the development of tools and mechanisms for the improved application of the lessons learned. Consequently, a so-called “European Clearinghouse” on NPP OEF was established, which includes scientific officers from the EC JRC, a number of European nuclear safety regulatory authorities and some of their Technical Support Organizations (TSOs). The paper discusses the activities implemented in 2008 within the framework of the European Clearinghouse on NPP OEF (hereinafter called the European NPP Clearinghouse) and provides an overview of the main conclusions drawn from the safety studies performed. Outlook of the activities carried out in 2009 are given.
Kurzfassung
Lernen aus der Betriebserfahrung und kurzfristige und vernünftige Anwendung dieser Erkenntnisse ist ein Weg, um die Sicherheit von Kernkraftwerken (KKW) zu verbessern. Kürzlich durchgeführte Überprüfungen der Effektivität der Systeme für den betrieblichen Erfahrungsrückfluss hat die Notwendigkeit für weitere Verbesserungen aufgezeigt. Dabei ist es notwendig, die Informationen auf die Bedürfnisse der Behörden zuzuschneiden. Auf Wunsch einer Reihe von kerntechnischen Sicherheitsbehörden in Europa hat im Jahr 2007 das Institut für Energie des Forschungszentrums EC JRC der Europäischen Kommission ein Projekt zum Rückfluss der Betriebserfahrungen von Kernkraftwerken initiiert. Dieses Projekt wendet einen integrierten Ansatz zur notwendigen Forschung an, um die europäische Leistungsfähigkeit zur Beurteilung von Betriebsereignissen in KKW zu erhöhen und die Entwicklung von Methoden und Mechanismen für die verbesserte Anwendung der gewonnenen Erfahrungen zu fördern. Daher wurde ein Europäisches Clearinghouse für den Rückfluss der Betriebserfahrungen von Kernkraftwerken eingerichtet, das aus wissenschaftlichen Mitarbeitern des Forschungszentrums, einer Reihe von kerntechnischen Sicherheitsbehörden sowie einiger ihrer Gutachterorganisationen besteht. Das Papier beschreibt die Aktivitäten in 2008 innerhalb des Rahmens für das Europäische Clearinghouse und gibt einen Überblick über die wesentlichen Ergebnisse der durchgeführten Studien. Außerdem wird ein Ausblick auf die geplanten Aktivitäten 2009 gegeben.
References
1 IAEA, 2008: Improving the International System for Operating Experience Feedback, INSAG Series No. 23Suche in Google Scholar
2 IAEA, 2007: Proceedings of Conference on Improving Nuclear Safety through Operating Experience Feedback, Cologne, Germany, June 2006Suche in Google Scholar
3 Ranguelova, V.: EC JRC, IE Network Research Activities on NPP Operational Experience Feedback. Proceedings from TOPSAFE 2008, CroatiaSuche in Google Scholar
4 Ross-Lee, M. J.: US NRC Clearinghouse on Operational Experience. Proceedings of the Conference on Improving Nuclear Safety through Operating Experience Feedback, Cologne, Germany, June 2006Suche in Google Scholar
5 OECD/NEA: Nuclear Power Plant Operating Experiences from IAEA/NEA Incident Reporting System 2002–2205: OECD/NEA, ISBN 92-64-02294-5, Paris, 2006Suche in Google Scholar
6 Duchac, A.: Report on the event of 25 July 2006 at the Forsmark Nuclear Power Plant Unit 1 in Sweden and the Countries' Responses to the Event. EC JRC, IE Petten, Report posted at the IAEA/IRS web site, 2008Suche in Google Scholar
7 Bruynooghe, Ch.: Report on incidents related to reactivity management. Example of the Shika-1 event on June 18th 1999 and Countries' Responses to the Event. EC JRC, IE Petten, Report posted at the IAEA/IRS web site, 2008Suche in Google Scholar
8 IAEA: Convention on Nuclear Safety. Information Circular INFCIRC/449, 5 July 1994Suche in Google Scholar
9 IAEA: International Nuclear Event Scale, 2004, http://www.iaea.org/Publications/Factsheets/English/ines.pdfSuche in Google Scholar
© 2010, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- European clearinghouse on nuclear power plants operational experience feedback
- Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor
- Heat transfer to the building structures of the Ignalina NPP accident localisation system
- Algorithmic determination of fuel rod cladding burst time at elevated temperatures
- Development of a decommissioning strategy for the MR research reactor
- Neutron transmutation doping conceptual design
- Design optimization of shell-and-tube heat exchangers using single objective and multiobjective particle swarm optimization
- Chebyshev polynomials expansion method for solving the one-dimensional transport equation in spherical geometry
- Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering
- An analytical solution for the one-dimensional time-dependent SN transport equation for bounded and unbounded domains in cartesian geometry
- Accurate critical slab calculations for various degrees of anisotropy and for different reflection coefficients
- Technical Notes/Technische Mitteilungen
- The boundary problem in the 1D-CANDLE burn-up reactor
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- European clearinghouse on nuclear power plants operational experience feedback
- Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor
- Heat transfer to the building structures of the Ignalina NPP accident localisation system
- Algorithmic determination of fuel rod cladding burst time at elevated temperatures
- Development of a decommissioning strategy for the MR research reactor
- Neutron transmutation doping conceptual design
- Design optimization of shell-and-tube heat exchangers using single objective and multiobjective particle swarm optimization
- Chebyshev polynomials expansion method for solving the one-dimensional transport equation in spherical geometry
- Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering
- An analytical solution for the one-dimensional time-dependent SN transport equation for bounded and unbounded domains in cartesian geometry
- Accurate critical slab calculations for various degrees of anisotropy and for different reflection coefficients
- Technical Notes/Technische Mitteilungen
- The boundary problem in the 1D-CANDLE burn-up reactor
