Ductile-to-brittle transition of oxidised Zircaloy-4 and E110 claddings

Journal of Nuclear Materials

Volumn 373, Issue 1-3, 2008, Pages 415-423

  Hózer, Zoltán ^a   Gyori, Csaba ^b   Matus, Lajos ^a   Horváth, Márta ^a  

^a KFKI ATOMIC ENERGY RESEARCH INSTITUTE   (Hungary)

^b JOINT RESEARCH CENTRE   (Italy)

Author keywords

[No Author keywords available]

Indexed keywords

BRITTLENESS; CLADDING (COATING); DUCTILITY; ELASTIC DEFORMATION; EMBRITTLEMENT; NUCLEAR FUELS;

DUCTILE PLATEAU; NUCLEAR FUEL RODS; ROOM TEMPERATURE;

ZIRCONIUM ALLOYS;

EID: 37549056622     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2007.07.002     Document Type: Article

References (19)

1. Hózer Z., Gyo{combining double acute accent}ri Cs., Horváth M., Nagy I., Maróti L., Matus L., Windberg P., and Frecska J. Nucl. Technol. 152 (2005) 273
2. Erbacher F.J. Nucl. Eng. Des. 103 (1987) 55
3. G. Hache, H.M. Chung, in: NUREG/CP-0172, 2001, p. 205.
4. D.O. Hobson, in: Proceedings of the ANS Topical Meeting on Water Reactor Safety, Salt Lake City, 1973, p. 274.
5. Yu.K. Bibilashvili, N.B. Sokolov, L.N. Andreeva-Andrievskaya, V.Yu. Tonkov, A.V. Salatov, A.M. Morosov, V.P. Smirnov, in: IAEA-TECDOC-1320, International Atomic Energy Agency, 2002, p. 186.
6. F. Nagase, M. Tanimoto, H. Uetsuka, in: IAEA-TECDOC-1320, International Atomic Energy Agency, 2002, p. 270.
7. Kim J.H., Lee M.H., Choi B.K., and Jeong Y.H. Nucl. Eng. Des. 235 (2005) 67-75
8. Valo M., Wallin K., Lucon E., Kytka M., Brumovsky M., Acosta B., Debarberis L., Kohopaa J., Gillemot F., and Horváth M. Nucl. Eng. Des. 235 (2005) 445
9. Ballesteros A., Bros J., Debarberis L., Sevini F., Erak D., Gezashchenko S., Kryukov A., Shtrombakh Y., Goloshapov S., Ionov A., Anikeev Y., Banyuk G., Plusch A., Gillemot F., Tatar L., and Petrosyan V. Nucl. Eng. Des. 235 (2005) 411
10. Chao Y.J., Ward Jr. J.D., and Sands R.G. Mater. Des. 28 (2007) 551
11. Bayraktar E., Hugele D., Jansen J.P., and Kaplan D. Mater. Proc. Technol. 147 (2004) 155-162
12. Böhmert J., Dietrich M., and Linek J. Nucl. Eng. Des. 147 (1993) 53
13. Z. Hózer, L. Matus, M. Horváth, L. Vasáros, Á. Griger, L. Maróti, Ring compression tests with oxidised and hydrided Zr1%Nb and Zircaloy-4 claddings, KFKI-2002-01/G KFKI, Atomic Energy Research Institute, 2002.
14. L. Yegorova, K. Lioutov, N. Jouravkova, A. Konobeev, V. Smirnov, V. Chesanov, A. Goryachev, US Nuclear Regulatory Commission, Experimental Study of Embrittlement of Zr-1%Nb VVER Cladding under LOCA-Relevant Conditions, NUREG/IA-0211, 2005.
15. I. Solyany, Yu. K. Bibliashvili, V.V. Dranenko, A.Ya. Levin, L.B. Izraljevskij, A.M. Morozov, in: IAEA-IWGFPT/19, International Atomic Energy Agency, 1984.
16. V. Vrtilkova, L. Novotny, V. Hamouz, R. Doucha, I. Tinka, J. Macek, F. Lahovsky, in: Proceedings of the International Conference on Nuclear Energy for New Europe, Bled, Slovenia, 2005, Paper No. 49.
17. Leistikow S., and Schanz G. Nucl. Eng. Des. 103 (1987) 65
18. J. Frecska, G. Konczos, L. Maróti, L. Matus, Oxidation and hydriding of Zr1%Nb alloy by steam, KFKI-1995-17/G, KFKI Atomic Energy Research Institute, 1995.
19. C. Vitanza, Discussion on experimental methods to derive LOCA safety limits, in: IAEA-TECDOC-1320, International Atomic Energy Agency, 2002, p. 224.