High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110

Journal of Nuclear Materials

Volumn 393, Issue 3, 2009, Pages 433-448

  Yan, Y ^a   Burtseva, T A ^a   Billone, M C ^a  

^a ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BREAK-AWAY OXIDATION; CLADDING ALLOYS; GAIN COEFFICIENTS; HIGH TEMPERATURE; HYDROGEN UPTAKE; LOSS-OF-COOLANT ACCIDENT; OXIDATION BEHAVIORS; SURFACE CONDITIONS; SURFACE IMPURITIES;

ALLOYS; HYDROGEN; LIGHT WATER REACTORS; NIOBIUM; NIOBIUM ALLOYS; POLISHING; TUBING; ZIRCONIUM;

OXIDATION;

EID: 69549107635     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2009.06.029     Document Type: Article

References (28)

1. L. Baker, L.C. Just, Studies of Metal-Water Reactions at High Temperatures: III. Experimental and Theoretical Studies of the Zirconium-Water Reaction, ANL-6548, May 1962.
2. J.V. Cathcart, R.E. Pawel, R.A. McKee, R.E. Druschel, G.J. Yurek, J.J. Campbell, S.H. Jury, Zirconium Metal-Water Oxidation Kinetics: IV. Reaction Rate Studies, ORNL/NUREG-17, August 1977.
3. Leistikow S., and Schanz G. Werkstoffe und Korrosion 36 (1985) 105
4. Leistikow S., and Schanz G. Nucl. Eng. Des. 103 (1987) 65
5. Chung H.M., and Kassner T.F. J. Nucl. Mater. 84 (1979) 327
6. Y. Yan, R.V. Strain, T.S. Bray, M.C. Billone, High Temperature Oxidation of Irradiated Limerick BWR Cladding, NUREG/CP-0176, May 2002, pp. 353-372.
7. G. Hache, H.M. Chung, The History of LOCA Embrittlement Criteria, NUREG/CP-0172, May 2001, pp. 205-237.
8. Kawasaki S., Furyta T., and Suzuki M. Nucl. Sci. Tech. 15 (1978) 589
9. Nagase F., Otomo T., and Uetsuka H. Nucl. Sci. Tech. 40 (2003) 213
10. Mardon J.-P., Charquet D., and Senevat J. Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy. In: Sabol G.P., and Moan G.D. (Eds). Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354 (2000), American Society for Testing and Materials, West Conshohocken, PA 505-524
11. R.J. Comstock, G. Schoenberger, G.P. Sabol, Influence of processing variables and alloy chemistry on the corrosion behavior of ZIRLO nuclear fuel cladding, in: E.R. Bradley, G.P. Sabol (Eds.), Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, American Society for Testing and Materials, 1996, pp. 710-725.
12. Shebaldov P.V., Peregud M.M., Nikulina A.V., Bibilashvilli Y.K., Lositski A.F., Kuz'menko N.V., Belov V.I., and Novoselov A.E. E1110 alloy cladding tube properties and their interrelation with alloy structure-phase condition and impurity content. In: Sabol G.P., and Moan G.D. (Eds). Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354 (2000), American Society for Testing and Materials, West Conshohocken, PA 545-559
13. ™ Cladding after High Temperature Oxidation in Steam, NEA/CSNI/R(2001)18, OECD Nuclear Agency, December 2001, pp. 135-143.
14. L. Yegorova, K. Lioutov, N. Jouravkova, A. Konobeev, V. Smirnov, V. Chesanov, A. Goryachev, Experimental Study of Embrittlement of Zr-1%Nb VVER Cladding under LOCA-Relevant Conditions, NUREG/IA-0211, March 2005.
15. Y. Yan, T. Burtseva, M.C. Billone, LOCA Results for Advanced-Alloy and High-Burnup Zircaloy Cladding, NUREG/CP-0185, June 2004, pp. 97-121.
16. ™ and Zircaloy-4 Alloys under LOCA Conditions, ICONE13-50457, in: 13th Intl. Conf. on Nucl. Eng., Beijing, China, May 16-20, 2005, pp. 1-9.
17. ™ (ZrNbO) Alloys During the First Phase of LOCA Transient, in: G.D. Moan, P. Rudling (Eds.), Zirconium in the Nuclear Industry, ASTM STP 1423, American Society for Testing and Materials, 2002, pp. 673-701.
18. M. Billone, Y. Yan, T. Burtseva, R. Daum, Cladding Embrittlement During Postulated Loss-of-Coolant Accidents, NUREG/CR-6967, ANL-07/04, July 2008.
19. J. Boehmert, M. Dietrich, J. Linek, Comparative studies on high-temperature corrosion of Zr-1%Nb and zircaloy-4, Nucl. Eng. Des., 147(1) (1993).
20. Baek J.H., Park K.B., and Jeong Y.H. J. Nucl. Mater. 335 (2004) 443
21. Nagase F., and Fuketa T. Nucl. Sci. Tech. 42 (2005) 209
22. ™ alloys in LOCA conditions, J. ASTM Intl., 2(2) Paper JAI12468 (2005).
23. ® alloys in LOCA conditions, J. ASTM Intl., 5(5) (2008). Available online as JAI101116 at .
24. Hozer Z., Gyori C., Matus L., and Horvath M. J. Nucl. Mater. 373 (2008) 415
25. ™ Behavior in LOCA, in: Proc. Topical Meeting on LOCA Fuel Safety Criteria, NEA/CSNI/R(2001) 18, OECD Nuclear Agency, 2001, pp. 105-133.
26. V.N. Shishov, A.V. Nikulina, V.A. Markelov, M.M. Peregud, A.V. Kozlov, S.A. Averin, S.A. Kolbenkov, A.Ye. Novoselov, Influence of Neutron Irradiation on Dislocation Structure and Phase Composition of Zr-Base Alloys, in: 11th International Symposium on Zirconium in the Nuclear Industry, Garmish-Parten-Kirhen, Germany, September 11-14 1995, ASTM STP 1295, American Society for Testing and Materials, 1996, pp. 603-621.
27. V. Nikulina, L.N. Andreeva-Andrievskaya, V.N. Shishov, Yu.V. Pimenov, Influence of Chemical Composition of Nb Containing Zr Alloy Cladding Tubes on Embrittlement under Conditions Simulating Design Basis LOCA, in: Presentation at the 14th Intl. Symp. on Zirconium in the Nuclear Industry, Stockholm, Sweden, June 13-17, 2004, available upon request.
28. H.M. Chung, The Effects of Aliovalent Elements on Nodular Corrosion, in: Proc. 2003 Nuclear Safety Research Conference, NUREG/CP-0185, 2004, pp. 283-298.