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.
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References
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 2004
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 2004
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 USA
MAAP4 — Modular Accident Analysis Program for LWR Power Plants. Volumes 1-4, Research Project 3131-02, May 1994, Fauske Associates, Inc., Rev. 0.0
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© 2004 Springer-Verlag London
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Bareith, A., Karsa, Z., Lajtha, G., Siklóssy, P., Téchy, Z., Elter, J. (2004). Development of a Level 2 PSA Model for the Paks NPP. In: Spitzer, C., Schmocker, U., Dang, V.N. (eds) Probabilistic Safety Assessment and Management. Springer, London. https://doi.org/10.1007/978-0-85729-410-4_283
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DOI: https://doi.org/10.1007/978-0-85729-410-4_283
Publisher Name: Springer, London
Print ISBN: 978-1-4471-1057-6
Online ISBN: 978-0-85729-410-4
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