Quenching of high temperature VVER fuel after long term oxidation in hydrogen rich steam

Annals of Nuclear Energy

Volumn 37, Issue 1, 2010, Pages 71-82

  Hózer, Zoltán ^a   Balaskó, Márton ^a   Horváth, Márta ^a   Kunstár, Mihály ^a   Matus, Lajos ^a   Nagy, Imre ^a   Novotny, Tamás ^a   Perez Feró, Erzsébet ^a   Pintér, Anna ^a   Vér, Nóra ^a   Vimi, András ^a   Windberg, Péter ^a  

^a KFKI ATOMIC ENERGY RESEARCH INSTITUTE   (Hungary)

Author keywords

[No Author keywords available]

Indexed keywords

CLEANING TANK INCIDENTS; COLD WATERS; FINAL STATE; FUEL RODS; HIGH TEMPERATURE; HYDROGEN CONCENTRATION; HYDROGEN UPTAKE; INTEGRAL TEST; LONG TERM; MAXIMUM TEMPERATURE; SEVERE FUEL DAMAGES; THERMAL CONDITION;

FUELS; GRAFTING (CHEMICAL); HYDROGEN; HYDROGEN EMBRITTLEMENT; OXIDATION; REACTOR CORES; SYNTHESIS (CHEMICAL); TANKS (CONTAINERS); ZIRCONIUM;

QUENCHING;

EID: 70449697855     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2009.09.014     Document Type: Article

References (27)

1. Bajsz, J., Gadó, J., 2004. Ex-core fuel damage event at Paks: causes, consequences and lessons learned. In: Proc. Int. Conf. Nuclear Energy for New Europe 2004. Portorož, Slovenia (Paper no. 901).
2. Chuto, T., Nagase, F., Fuketa, T., 2008. High temperature oxidation of Nb containing alloys in LOCA conditions. In: Proc. 2008 Water Reactor Fuel Performance Meeting. Soeul (Paper no. 8047).
3. Clément B., Hanniet-Girault N., Repetto G., Jacquemain D., Jones A.V., Kissane M.P., and von der Hardt P. LWR severe accident simulation: synthesis of the results and interpretation of the first PHEBUS FP experiment FPT0. Nucl. Eng. Des. 226 (2003) 5-82
4. Furuta T., Uetsuka H., and Kawasaki S. Ductility loss of zircaloy cladding by inner-surface oxidation during high temperature transient. J. Nucl. Sci. Technol. 18 (1981) 802-810
5. 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 .
6. Hofmann P., Hagen S.J.L., Noack V., Schanz G., and Sepold L.K. Chemical-physical behaviour of light water reactor core components tested under severe reactor accident conditions in the CORA facility. Nucl. Technol. 118 (1997) 200-224
7. Hofmann, P., Hering, W., Homann, C., Leining, W., Miassoedov, A., Piel, D., Schmidt, L., Sepold, L., Steinbrück, M., 1998. QUENCH-01 experimental and calculational results. FZKA 6100, Forschungszentrum Karlsruhe.
8. Hózer Z., Windberg P., Nagy I., Maróti L., Matus L., Horváth M., Pintér A., Balaskó M., Czitrovszky A., and Jani P. Interaction of failed fuel rods under air ingress conditions. Nucl. Technol. 141 (2003) 244-256
9. Hózer Z., Maróti L., Windberg P., Matus L., Nagy I., Gyenes Gy., Horváth M., Pintér A., Balaskó M., Czitrovszky A., Jani P., Nagy A., Prokopiev O., and Tóth B. Behaviour of VVER fuel rods tested under severe accident conditions in the CODEX facility. Nucl. Technol. 154 (2006) 302-317
10. Hózer Z., Gadó J., Somfai B., Szabó E., Elter J., and Nagy L. Safety analysis of a VVER-440 spent fuel storage pool. Int. J. Nucl. Energy Sci. Technol. 3 (2007) 302-313
11. Hózer, Z., Windberg, P., Nagy, I., Matus, L., Vér, N., Kunstár, M., Vimi, A., Novotny, T., Perez-Feró, E., Horváth, M., Pintér, A., Balaskó, M., 2008a. CODEX-CT-1 experiment: quenching of fuel bundle after long term oxidation in hydrogen rich steam, KFKI-1/2008.
12. Hózer, Z., Windberg, P., Nagy, I., Matus, L., Vér, N., Kunstár, M., Vimi, A., Horváth, M., Novotny, T., Perez-Feró, E., Pintér, A., Balaskó, M., 2008b. CODEX-CT-2 Experiment: long term treatment in high temperature hydrogen and water quenching of a fuel bundle, KFKI-2/2008.
13. Hózer Z., Gyo{combining double acute accent}ri Cs., Matus L., and Horváth M. Ductile-to-brittle transition of oxidized zircaloy-4 and E110 claddings. J. Nucl. Mater. 373 (2008) 415-423
14. Kim J.H., Choi B.K., Baek J.H., and Jeong Y.H. Effects of oxide and hydrogen on the behaviour of zircaloy-4 cladding during the loss of the coolant accident (LOCA). Nucl. Eng. Des. 236 (2006) 2386-2393
15. Kunstár M., Matus L., Vér N., Pintér A., Hózer Z., Steinbrück M., and Stuckert J. Experimental investigation of the late phase of spent fuel pool accidents. Int. J. Nucl. Energy Sci. Technol. 3 (2007) 287-301
16. Miassoedov A., Alsmeyer H., Meyer L., Steinbrück M., Groudev P., Ivanov I., and Sdouz G. Results of the QUENCH-L2, DISCO-L2, and COMET-L2 experiments performed within the LACOMERA project at the Forschungszentrum Karlsruhe. Nucl. Eng. Des. 238 (2008) 2017-2026
17. OECD-IAEA Paks fuel project final report. 2008. NEA/CSNI/R(2008)2.
18. Perez-Feró, E., Windberg, P., Hózer, Z., Horváth, M., Nagy, I., Pintér-Csordás, A., Szabó, E., Kulacsy, K., 2006. Experimental database of E110 cladding oxidized in hydrogen rich steam. In: Transactions of TOPFUEL, Poster Session II, pp. 112-116.
19. Perez-Feró, E., Hózer, Z., Windberg, P., Nagy, I., Vimi, A., Vér, N., Matus, L., Kunstár, M., Novotny, T., Horváth, M., Gyo{combining double acute accent}ri, Cs., 2007. Behaviour of Zr1%Nb fuel cladding under accident conditions. In: Proc. Int. LWR Fuel Performance Meeting, San Francisco (Paper 1018).
20. Schanz G., Hagen S., Hofmann P., Schumacher G., and Sepold L. Information on the evolution of severe LWR fuel element damage obtained in the CORA program. J. Nucl. Mater. 188 (1992) 131-145
21. Schwarz M., Hache G., and von der Hardt P. PHEBUS FP: a severe accident research programme for current and advanced light water reactors. Nucl. Eng. Des. 187 (1999) 47-69
22. Schwarz M., Clement B., and Jones A.V. Applicability of PHEBUS FP results to severe accident safety evaluations and management measures. Nucl. Eng. Des. 209 (2001) 173-181
23. Smirnov, A., Markov, D., Smirnov, V., Polenok, V., Ivashchenko, A.,Strozhuk, A., 2005. Results of post-irradiation examination of WWER fuel assembly structural components made of E-110 and E-635 alloys. In: Proc. 6th Int. Conf. on WWER Fuel Performance, Modelling and Experimental Support, Albena, pp. 231-243.
24. Steinbrück M., Miassoedov A., Schanz G., Sepold L., Stegmaier U., and Stuckert J. Experiments on air ingress during severe accidents in LWRS. Nucl. Eng. Des. 236 (2006) 1709-1719
25. Stuckert J., Birchley J., Große M., Haste T., Sepold L., and Steinbrück M. Experimental and post-test calculation results of the integral reflood test QUENCH-12 with a VVER-type bundle. Ann. Nucl. Energy 36 (2009) 183-192
26. 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.
27. 2 Fuel (VVER Type) under reactivity accident conditions, NUREG/IA-0156, 1 (IPSN99/08-02, NSI/RRC KI 2179).