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

4 Citations (Scopus)

Abstract

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
Volume240
Issue number3
DOIs
Publication statusPublished - 2010
MoE publication typeA1 Journal article-refereed

Fingerprint

OECD
Cooling
cooling
inlet flow
oxidation
Oxidation
Inlet flow
fission products
Fission products
accidents
Zirconium
hydraulics
assemblies
simulation
accident
project
Hydrogen
Accidents
rods
flow velocity

Cite this

Hózer, Z., Aszódi, A., Barnak, M., Boros, I., Fogel, M., Guillard, V., ... Zvonarev, Y. (2010). Numerical analyses of an ex-core fuel incident: Results of the OECD-IAEA Paks Fuel Project. Nuclear Engineering and Design, 240(3), 538-549. https://doi.org/10.1016/j.nucengdes.2009.09.031
Hózer, Z. ; Aszódi, A. ; Barnak, M. ; Boros, I. ; Fogel, M. ; Guillard, V. ; Győri, Cs. ; Hegyi, G. ; Horváth, G.L. ; Nagy, I. ; Junninen, Pasi ; Kobzar, V. ; Légrádi, G. ; Molnár, A. ; Pietarinen, Kari ; Perneczky, L. ; Makihara, Y. ; Matejovic, P. ; Perez-Ferò, E. ; Slonszki, E. ; Tóth, I. ; Trambauer, K. ; Tricot, N. ; Troszterl, I. ; Verpoorten, J. ; Vitanza, A. ; Voltchek, K. ; Wagner, K.C. ; Zvonarev, Y. / Numerical analyses of an ex-core fuel incident : Results of the OECD-IAEA Paks Fuel Project. In: Nuclear Engineering and Design. 2010 ; Vol. 240, No. 3. pp. 538-549.
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abstract = "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.",
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Hózer, Z, Aszódi, A, Barnak, M, Boros, I, Fogel, M, Guillard, V, Győri, C, Hegyi, G, Horváth, GL, Nagy, I, Junninen, P, Kobzar, V, Légrádi, G, Molnár, A, Pietarinen, K, Perneczky, L, Makihara, Y, Matejovic, P, Perez-Ferò, E, Slonszki, E, Tóth, I, Trambauer, K, Tricot, N, Troszterl, I, Verpoorten, J, Vitanza, A, Voltchek, K, Wagner, KC & Zvonarev, Y 2010, 'Numerical analyses of an ex-core fuel incident: Results of the OECD-IAEA Paks Fuel Project', Nuclear Engineering and Design, vol. 240, no. 3, pp. 538-549. https://doi.org/10.1016/j.nucengdes.2009.09.031

Numerical analyses of an ex-core fuel incident : Results of the OECD-IAEA Paks Fuel Project. / Hózer, Z. (Corresponding Author); Aszódi, A.; Barnak, M.; Boros, I.; Fogel, M.; Guillard, V.; Győri, Cs.; Hegyi, G.; Horváth, G.L.; Nagy, I.; Junninen, Pasi; Kobzar, V.; Légrádi, G.; Molnár, A.; Pietarinen, Kari; Perneczky, L.; Makihara, Y.; Matejovic, P.; Perez-Ferò, E.; Slonszki, E.; Tóth, I.; Trambauer, K.; Tricot, N.; Troszterl, I.; Verpoorten, J.; Vitanza, A.; Voltchek, K.; Wagner, K.C.; Zvonarev, Y.

In: Nuclear Engineering and Design, Vol. 240, No. 3, 2010, p. 538-549.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Numerical analyses of an ex-core fuel incident

T2 - Results of the OECD-IAEA Paks Fuel Project

AU - Hózer, Z.

AU - Aszódi, A.

AU - Barnak, M.

AU - Boros, I.

AU - Fogel, M.

AU - Guillard, V.

AU - Győri, Cs.

AU - Hegyi, G.

AU - Horváth, G.L.

AU - Nagy, I.

AU - Junninen, Pasi

AU - Kobzar, V.

AU - Légrádi, G.

AU - Molnár, A.

AU - Pietarinen, Kari

AU - Perneczky, L.

AU - Makihara, Y.

AU - Matejovic, P.

AU - Perez-Ferò, E.

AU - Slonszki, E.

AU - Tóth, I.

AU - Trambauer, K.

AU - Tricot, N.

AU - Troszterl, I.

AU - Verpoorten, J.

AU - Vitanza, A.

AU - Voltchek, K.

AU - Wagner, K.C.

AU - Zvonarev, Y.

PY - 2010

Y1 - 2010

N2 - 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.

AB - 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.

U2 - 10.1016/j.nucengdes.2009.09.031

DO - 10.1016/j.nucengdes.2009.09.031

M3 - Article

VL - 240

SP - 538

EP - 549

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

IS - 3

ER -