Current international activities to increase fire protection knowledge for nuclear power plants
-
H. P. Berg
Abstract
For nuclear power plants fire events are of high safety significance since they have the potential to damage more than one redundant safety train simultaneously. Within the frame of the recently started second series of periodic safety reviews, a probabilistic fire risk assessment has to be performed in addition to the deterministic analysis. Therefore, realistic fire occurrence frequencies as well as appropriate validated fire models and simulation codes are needed. All these complex issues require internationally harmonized activities to gain consistent, reliable and traceable information as well as to reduce the costs. Presently, three international activities are ongoing: the OECD-FIRE project with the goal to establish a quality assured and consistent international fire event database, and two further activities. In the frame of one of these fire models and computer codes shall be evaluated and validated based on real scale experiments under as far as possible realistic boundary conditions in order to support their extended use for decision making. The other one aims on analyzing fire induced electric failures of safety related systems and components. The objectives of the international co-operations and the first results are presented.
Kurzfassung
Brände in kerntechnischen Anlagen sind von hoher sicherheitstechnischer Bedeutung, weil sie redundanzübergreifend zum Ausfall sicherheitstechnisch wichtiger Komponenten und Systeme führen können. Da in der jetzt anlaufenden zweiten Runde der Sicherheitsüberprüfungen neben der deterministischen auch eine probabilistische Brandanalyse durchzuführen ist, sind Daten zur Ermittlung einer möglichst realistischen Brandeintrittshäufigkeit notwendig, aber auch validierte Rechenprogramme und geeignete Brandmodelle. Diese sehr komplexen Fragestellungen erfordern internationale Projekte, um entsprechend belastbare Informationen zu erhalten und die Aktivitäten finanzierbar zu machen. Neben dem Projekt OECD-FIRE, in dem eine qualitätsgesicherte und konsistente Branddatenbasis aufgebaut werden soll, bestehen derzeit zwei weitere Projekte. Im ersteren sollen anhand von realmaßstäblichen Brandversuchen unter weitestgehend realistischen Randbedingungen Brandmodelle und Rechenprogramme im Hinblick auf deren Einsatz für regulatorische Entscheidungen validiert und bewertet werden. Das andere Projekt hat Untersuchungen für eine probabilistische Behandlung eines brandbedingten Versagens sicherheitsrelevanter elektrischer Komponenten zum Ziel. Ziele der internationalen Kooperationen sowie die bisherigen Ergebnisse werden dargestellt.
References
1 Organisation for Economic Co-operation and Development (OECD/NEA/CSNI): Proceedings from International Workshop on Fire Risk Assessment, Helsinki, 29 June – 2 July 1999, NEA/CSNI/R (99) 26, OECD, Paris, June2000.Search in Google Scholar
2 Dey, M. K.: International Collaborative Project to Evaluate Fire Models for Nuclear Power Plant Applications: Summary of Planning Meeting, NUREG/CP-0170, U.S. Nuclear Regulatory Commission, Washington, DC, April2000.Search in Google Scholar
3 LaChance, J. L.; Nowlen, S. P.; Wyant, F. J.;. Dandini, V. J.: Circuit Analysis – Failure Mode and Likelihood Analysis, NUREG/CR-6834, SAND 2002-1942 P, September2003.Search in Google Scholar
4 COOPRA Working Group on Fire-Induced Damage to Electrical Cables and Circuits (FIDECC): White paper related to Fire-Induced Damage to Electrical Cables and Circuits, 2002.Search in Google Scholar
5 Dey, M. K.et al.: Evaluation of Fire Models for Nuclear Power Plant Applications: Cable Tray Fires International Panel Report, NISTR 6872, June2002http://fire.nist.gov/bfrlpubs/fire02/PDF/f02039.pdf.10.6028/NIST.IR.6872Search in Google Scholar
© 2004, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Sensitivity analysis of the Peach Bottom Turbine Trip 2 experiment
- Theoretical and experimental investigations into natural circulation behaviour in a simulated facility of the Indian PHWR under reduced inventory conditions
- A new data-condensation method based on multidimensional minimisation
- Current international activities to increase fire protection knowledge for nuclear power plants
- Simple formulas for conservatively calculating the fuel rod cladding strains due to RIA
- Accelerator driven systems for transmutation and energy production: challenges and dangers
- A method for in-situ quantification of oxygen in oil using fast neutron activation analysis
- The time-dependent effect of the biological component of 137Cs soil contamination
- Letter to the Editor
- Remarks on pulsed neutron activation
- On the critical radius of reflected spheres
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Sensitivity analysis of the Peach Bottom Turbine Trip 2 experiment
- Theoretical and experimental investigations into natural circulation behaviour in a simulated facility of the Indian PHWR under reduced inventory conditions
- A new data-condensation method based on multidimensional minimisation
- Current international activities to increase fire protection knowledge for nuclear power plants
- Simple formulas for conservatively calculating the fuel rod cladding strains due to RIA
- Accelerator driven systems for transmutation and energy production: challenges and dangers
- A method for in-situ quantification of oxygen in oil using fast neutron activation analysis
- The time-dependent effect of the biological component of 137Cs soil contamination
- Letter to the Editor
- Remarks on pulsed neutron activation
- On the critical radius of reflected spheres
