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

Nuclear Engineering and Design

Volumn 240, Issue 3, 2010, Pages 538-549

  Hozer Z ^a   Aszodi A ^b   Barnak, M ^c   Boros, I ^b   Fogel, M ^d   Guillard, V ^e   Gyori, Cs ^f   Hegyi, G ^a   Horvath G L ^g   Nagy, I ^a   Junninen, P ^h   Kobzar, V ⁱ   Legradi G ^b   Molnar A ^a   Pietarinen, K ^h   Perneczky, L ^a   Makihara, Y ^j   Matejovic, P ^c   Perez Fero E ^a   Slonszki, E ^a   Toth I ^a   Trambauer, K ^k   Tricot, N ^l   Trosztel, I ^a   Verpoorten, J ^m   Vitanza, C ⁿ   Voltchek, A ⁱ   Wagner, K C ^o   Zvonarev, Y ⁱ   more..

^a KFKI ATOMIC ENERGY RESEARCH INSTITUTE   (Hungary)

^b BUDAPEST UNIVERSITY OF TECHNOLOGY AND ECONOMICS   (Hungary)

^c IVS   (Slovakia)

^d VUJE   (Slovakia)

^e INSTITUT DE RADIOPROTECTION ET DE SÛRETÉ NUCLÉAIRE IRSN   (France)

^f ITU   (Germany)

^g VEIKI Institute for Electric Power Research   (Hungary)

^h VTT TECHNICAL RESEARCH CENTRE OF FINLAND   (Finland)

ⁱ RRC KI   (Russian Federation)

^j ATMEA   (France)

^k GESELLSCHAFT FÜR ANLAGEN UND REAKTORSICHERHEIT GRS MBH   (Germany)

^l INTERNATIONAL ATOMIC ENERGY AGENCY   (Austria)

^m TRACTEBEL ENGINEERING   (Belgium)

ⁿ OECD   (France)

^o SANDIA NATIONAL LABORATORIES   (United States)

more..

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT CONDITIONS; CODE CALCULATIONS; COOLING CONDITIONS; DEGRADATION MECHANISM; FUEL ASSEMBLY; FUEL FAILURE; FUEL RODS; INLET FLOW RATE; MAXIMUM TEMPERATURE; MEASURED DATA; NUMERICAL SIMULATION; THERMAL-HYDRAULIC CALCULATIONS; ZIRCONIUM OXIDATION;

COMPUTER SIMULATION; DEGRADATION; FISSION PRODUCTS; INLET FLOW; NUMERICAL ANALYSIS; OXIDATION; ZIRCONIUM;

FUELS;

EID: 75149182229     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2009.09.031     Document Type: Article

References (27)

1. Aksan, N., 2008. International Standard problems and small break loss-of-coolant accident (SBLOCA), Sci. Technol. Nucl. Installations 2008, doi:10.1155/2008/814572 (article ID 814572).
2. Austregesilo, H., Bals, C., Hora, A., Lerchl, G., Romstedt, P., 2003. ATHLET Mod 2.0 Cycle A-Models and Methods, vol. 4. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, GRS-P-1.
3. ANSYS, 2005. ANSYS CFX Products 10.0, Canonsburg.
4. Bajsz J., and Gadó J. Ex-core fuel damage event at paks-causes, consequences and lessons learned. Proc. Int. Conf. Nuclear Energy for New Europe 2004. Portorož (2004) Paper 901
5. Chatelard, P., Coindreau, O., Drai, P., Fichot, F., Guillard, G., Marchand O., 2008, ICARE2 V3mod2.1 and ICARE/CATHARE V2.2. Release guide and code evolution overview, Technical note IRSN/DPAM/SEMCA, 2007-331, January 2008.
6. Cunningham M.E., Beyer C.E., Medvedev P.G., and Berna G.A. FRAPTRAN: A Computer Code for the Transient Analysis of Oxide Fuel Rods (2001), Pacific Northwest National Laboratory, Richland (NUREG/CR-6739, vol. 1, PNNL-13576)
7. Gauntt R.O., Cole R.K., Erickson C.M., Gido R.G., Gasser R.D., Rodriguez S.B., and Younget M.F. MELCOR Code Manuals: Reference Manuals Version 1.8.5, vol. 2, rev. 2 (2000), Sandia National Laboratories, NUREG/CR-6119, SAND2000-2417/1
8. HAEA, 2003. Report to the Chairman of the Hungarian Atomic Energy Commission on the Authority's Investigation of the Incident at Paks Nuclear Power Plant on 10 April 2003 (available on http://www.haea.gov.hu).
9. Hänninen, M., Ylijoki, J., 2008. The one-dimensional separate two-phase flow model of APROS. Espoo, VTT. 61 p. VTT Tiedotteita-Research Notes, 2443 (available on http://www.vtt.fi/inf/pdf/tiedotteet/2008/T2443.pdf).
10. Hózer Z., Windberg P., Nagy I., Vimi A., Vér N., Matus L., and Kunstár M. Experimental simulation of the Paks-2 cleaning tank incident. Transactions of SMiRT 19. Toronto (2007) paper C02/5
11. Hózer Z., Szabó E., Pintér T., Baracska Varjú I., Bujtás T., Farkas G., and Vajda N. Activity release from damaged fuel during the Paks-2 cleaning tank incident in the spent fuel storage pool. J. Nucl. Mater. 392 (2009) 90-94
12. Keresztúri A., Hegyi Gy., Hordósy G., Makai M., Maráczy Cs., and Telbisz M. KARATE-a code system for VVER-440 core calculations. Proceedings of the Fifth Symposium of AER. Dobogóko{combining double acute accent}, Hungary (1995) 403-421
13. Keresztúri A., Bogatyr S., Mikó S., and Nemes I. Analyses for licensing of new fuel types at NPP paks. Proc. WWER Fuel Performance Conference. Albena, Bulgaria, 29 September-3 October (2003) 243-252
14. Lanning D.D., Beyer C.E., and Painter C.L. FRAPCON-3: Modifications to Fuel Rod Material Properties and Performance Models for High-Burnup Application (1997), Pacific Northwest National Laboratory, Richland (NUREG/CR-6534, vol. 4, PNNL-11513)
15. Lassmann K. TRANSURANUS: a fuel rod analysis code ready for use. J. Nucl. Mater. 188 (1992) 295-302
16. Makihara Y. IAEA TC project "strengthening safety and reliability of fuel and materials in nuclear power plants". In: Stefanova S. (Ed). Proc. 7th Int. Conf. WWER Fuel Performance Modelling and Experimental Support, Institute of Nuclear Research and Nuclear Energy (2008) 35-44
17. OECD-IAEA Paks Fuel Project Final Report, 2008, NEA/CSNI/R(2008)2.
18. Perez-Feró, E., Gyo{combining double acute accent}ri, Cs., Matus, L., Vasáros, L., Hózer, Z., Windberg, P., Maróti, L., Horváth, M., Nagy, I., Pintér-Csordás, A., Novotny, T., 2008. Experimental Database of E110 Claddings under Accident Conditions, NEA-1799 IFPE/AEKI-EDB-E110.
19. The RELAP5 Code Development Team, 1995. RELAP5/MOD3.2.2 Manuals, NUREG/CR-5535-vols. I-VII.
20. Schanz G., Adroguer B., and Volchek A. Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations. Part I. Experimental database and basic modeling. Nucl. Eng. Des. 232 (2004) 75-84
21. Schunk J., Beier M., Kovács F., Mikó S., Tilky P., Berthold H.O., Janzik I., and Marquardt G. Fuel assembly chemical cleaning at paks nuclear power plant. IAEA-TECDOC-1345 (2003) 59-71
22. Stephenson, W., Dutton, L.M.C., Handy, B.J., Smedley, C., 1992. Realistic methods for calculating the releases and consequences of a large LOCA. EUR 17179 EN, EC.
23. Trambauer K., Bals C., Schubert J.D., and Austregesilo H. ATHLET-CD Mod 2.0-Cycle A User's Manual, GRS-P-4, vol. 1 (2004), Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH
24. Vámos, G., 2003. Investigation report on the fuel damage occurred on 10-11 April within the cleaning equipment of FANP, Report to OAH-NBI, NBI 03.11 B20301 (available on http://www.npp.hu).
25. Van Dorsselaere, J.P., Schwinges, B., 2006. Overview of the integral code ASTEC V1.3 rev.0, Report IRSN DPAM/ASTEC-2006-362, GRS ASTEC 06/02.
26. Vöröss, L., 2003. Lessons Learned from the INES-3 event at PAKS NPP on April 10, 2003, EUROSAFE Paris, November 25-26, Seminar 1 (available on http://www.eurosafe-forum.org/files/pe_125_24_1_seminaire_1_6.pdf).
27. Zvonarev Yu., Voltchek A., Kobzar V., Chatelard P., and Van Dorsselaere J.P. ASTEC and ICARE/CATHARE modeling improvement for VVERs. Accepted for Int. Conf. on Nuclear Energy for New Europe 2009 (NENE). Bled (Slovenia), 14-17 September (2009)