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Dynamic structure response due to reactor cooling piping system failure

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Published/Copyright: April 5, 2013
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Kerntechnik
From the journal Kerntechnik Volume 73 Issue 1-2

Abstract

The safety evaluation of the primary core cooling system requires an accurate hydraulic analysis of the system during normal and abnormal conditions. A model of the piping components of a common research reactor system is obtained and illustrated using the FE/PIPE Finite Element Package. Different accidents leading to a loss of the system function are investigated, such as pipe rupture and valve failure. The hydraulic-structure interaction and dynamic parameters responded to the accident are obtained during the transient time. The scenario time domain is selected to be very short (2.0 s) to get more conservative calculations and more safety margins in the final design. The results reflect that the natural system frequency should be in the margin greater than 34 Hz otherwise resonance with the generated forces during the accident will happen, that could lead to a system failure.

Kurzfassung

Die Sicherheitsbewertung des primären Kühlkreislaufs erfordert eine genaue hydraulische Analyse des Systems während normaler und abnormaler Betriebsbedingungen. Ein Modell der Rohrleitungskomponenten des Gesamtsystems eines Forschungsreaktors wird mit Hilfe der FE/PIPE Finite-Elemente-Methode dargestellt. Verschiedene Störfälle, die zu einem Verlust der Systemfunktion führen, werden untersucht, wie z. B. ein Rohrleitungsbruch oder ein Ventilversagen. Während der Transientenzeit erhält man die Wechselwirkung zwischen hydraulischen Strukturen und dynamischen Parametern, in Abhängigkeit vom unterstellten Störfall. Der Zeitbereich des Szenarios wurde sehr kurz gewählt (2.0 s), um mehr konservative Berechnungen und höhere Sicherheitsbereiche bei der endgültigen Auslegung zu erreichen. Die Ergebnisse zeigen, dass die natürliche Frequenz des Systems in einem Bereich größer als 34 Hz liegen sollte, da sonst Resonanzen zu einer Störung des Systems führen könnten.

References

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Received: 2007-8-8
Published Online: 2013-04-05
Published in Print: 2008-03-01

© 2008, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Analysis of the hydrogen behaviour in compartments of the Ignalina nuclear power plant
  7. Determination of the RBMK-1500 reactor passport characteristics
  8. Technical feasibility of using RU-43 fuel in the CANDU-6 reactors of the Cernavoda NPP
  9. Computational study of moderator flow and temperature fields in the calandria vessel of a heavy water reactor using the PHOENICS code
  10. Regulatory requirements on level 2 PSA in Germany and their associated potential to improve emergency management
  11. Dynamic structure response due to reactor cooling piping system failure
  12. Uncertainty in activation cross-section calculations at intermediate proton energies
  13. The LTSN solution of the transport equation for one-dimensional cartesian geometry with c = 1
  14. Application of the UN approximation to the neutron transport equation in slab geometry
  15. The reflected critical slab problem for one-speed neutrons with strongly anisotropic scattering
  16. The analytical representation of the fundamental mode in 1-D-geometry for the CANDLE burn-up phenomenon
https://doi.org/10.3139/124.100535

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Analysis of the hydrogen behaviour in compartments of the Ignalina nuclear power plant
  7. Determination of the RBMK-1500 reactor passport characteristics
  8. Technical feasibility of using RU-43 fuel in the CANDU-6 reactors of the Cernavoda NPP
  9. Computational study of moderator flow and temperature fields in the calandria vessel of a heavy water reactor using the PHOENICS code
  10. Regulatory requirements on level 2 PSA in Germany and their associated potential to improve emergency management
  11. Dynamic structure response due to reactor cooling piping system failure
  12. Uncertainty in activation cross-section calculations at intermediate proton energies
  13. The LTSN solution of the transport equation for one-dimensional cartesian geometry with c = 1
  14. Application of the UN approximation to the neutron transport equation in slab geometry
  15. The reflected critical slab problem for one-speed neutrons with strongly anisotropic scattering
  16. The analytical representation of the fundamental mode in 1-D-geometry for the CANDLE burn-up phenomenon
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