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Development of a Level 2 PSA Model for the Paks NPP

  • Attila Bareith
  • Zoltán Karsa
  • Gábor Lajtha
  • Péter Siklóssy
  • Zsolt Téchy
  • József Elter
Conference paper

Abstract

Level 2 probabilistic safety assessment (PSA) has recently been performed for the Paks NPP of Hungary. This paper highlights the main analysis steps as well as the approach used to develop and quantify the level 2 PSA model. Examples are given of the results from PSA model quantification with a note on usefulness and future implications of the study.

Keywords

Damage State Severe Accident Safety Injection Core Damage Probabilistic Safety Assessment 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    Elter, J. Gadó, E. Holló: Main Results of a Level 2 PSA Study Completed for Paks NPP. Presented at PSAM 7 / ESREL’ 04, Berlin, 14–18 June 2004Google Scholar
  2. 2.
    Zs, Téchy, G. Lajtha: Modelling of Severe Accident Phenomena in Level 2 PSA for Paks NPP. Presented at PSAM 7 / EREL’ 04, Berlin, 14–18 June 2004Google Scholar
  3. 3.
    J. Elter, A. Bareith, E. Holló, Zs. Téchy: A Practical Approach to Integrate Level 1 and Level 2 PSA Models of a VVER-440/213 Type NPP. In: Probabilistic Safety Assessment and Management — PSAM 6, Proceedings, 23–28 June 2002, San Juan, Puerto Rico USAGoogle Scholar
  4. 4.
    MAAP4 — Modular Accident Analysis Program for LWR Power Plants. Volumes 1-4, Research Project 3131-02, May 1994, Fauske Associates, Inc., Rev. 0.0Google Scholar

Copyright information

© Springer-Verlag London 2004

Authors and Affiliations

  • Attila Bareith
    • 1
  • Zoltán Karsa
    • 1
  • Gábor Lajtha
    • 1
  • Péter Siklóssy
    • 1
  • Zsolt Téchy
    • 1
  • József Elter
    • 2
  1. 1.VEIKI Institute for Electric Power ResearchBudapestHungary
  2. 2.Paks Nuclear Power Plant Ltd.PaksHungary

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