Numerical analyses of an ex-core fuel incident: Results of the OECD-IAEA Paks Fuel Project

Z. Hózer (Corresponding Author), A. Aszódi, M. Barnak, I. Boros, M. Fogel, V. Guillard, Cs. Győri, G. Hegyi, G.L. Horváth, I. Nagy, Pasi Junninen, V. Kobzar, G. Légrádi, A. Molnár, Kari Pietarinen, L. Perneczky, Y. Makihara, P. Matejovic, E. Perez-Ferò, E. SlonszkiI. Tóth, K. Trambauer, N. Tricot, I. Troszterl, J. Verpoorten, A. Vitanza, K. Voltchek, K.C. Wagner, Y. Zvonarev

Research output: Contribution to journalArticleScientificpeer-review

5 Citations (Scopus)


The OECD-IAEA Paks Fuel Project was developed to support the understanding of fuel behaviour in accident conditions on the basis of analyses of the Paks-2 incident. Numerical simulation of the most relevant aspects of the event and comparison of the calculation results with the available data from the incident was carried out between 2006 and 2007. A database was compiled to provide input for the code calculations. The activities covered the following three areas: (a) Thermal hydraulic calculations described the cooling conditions possibly established during the incident. (b) Simulation of fuel behaviour described the oxidation and degradation mechanisms of the fuel assemblies. (c) The release of fission products from the failed fuel rods was estimated and compared to available measured data. The applied used codes captured the most important events of the Paks-2 incident and the calculated results improved the understanding of the causes and mechanisms of fuel failure. The numerical analyses showed that the by-pass flow leading to insufficient cooling amounted to 75–90% of the inlet flow rate, the maximum temperature in the tank was between 1200 and 1400 °C, the degree of zirconium oxidation reached 4–12% and the mass of produced hydrogen was between 3 and 13 kg.

Original languageEnglish
Pages (from-to)538-549
JournalNuclear Engineering and Design
Issue number3
Publication statusPublished - 2010
MoE publication typeA1 Journal article-refereed


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