Effect of beta-to-alpha phase transition rate on corrosion behaviour of Zircaloy

Corrosion Science

Volumn 48, Issue 5, 2006, Pages 1154-1181

  Massih, A R ^a,b   Dahlback M ^c   Limback M ^c   Andersson, T ^d   Lehtinen, B ^e  

^a Quantum Technologies   (Sweden)

^b MALMÖ UNIVERSITY   (Sweden)

^c WESTINGHOUSE ELECTRIC COMPANY   (United States)

^d SANDVIK MATERIALS TECHNOLOGY   (Sweden)

^e BL Electron Microscopy   (Sweden)

Author keywords

Boiling water reactors; Corrosion; Quenching rate; Second phase particles; Widmanst tten structure; Zr alloys

Indexed keywords

BOILING WATER REACTORS; CLADDING (COATING); CORROSION; CORROSION RESISTANCE; GRAIN SIZE AND SHAPE; PHASE TRANSITIONS; QUENCHING; SCANNING ELECTRON MICROSCOPY; TRANSMISSION ELECTRON MICROSCOPY;

QUENCHING RATE; SECOND PHASE PARTICLES; WIDMANSTÄTTEN STRUCTURE;

ZIRCONIUM ALLOYS;

BOILING WATER REACTORS; CLADDING (COATING); CORROSION; CORROSION RESISTANCE; GRAIN SIZE AND SHAPE; PHASE TRANSITIONS; QUENCHING; SCANNING ELECTRON MICROSCOPY; TRANSMISSION ELECTRON MICROSCOPY; ZIRCONIUM ALLOYS;

EID: 33646017414     PISSN: 0010938X     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.corsci.2005.05.010     Document Type: Article

References (41)

1. Lemaignan C., and Motta A.T. Zirconium alloys in nuclear applications. In: Cahn R.W., Haasen P., and Kramer E.J. (Eds). Nuclear Materials. In: Frost B.R.T. (Ed). Material Science and Technology vol. 10B (1994), VCH, Weinheim, Germany Chapter 7
2. Froes F.H., Tau T.-L., and Weidinger H.G. Titanium, zirconium and hafnium. In: Cahn R.W., Haasen P., and Kramer E.J. (Eds). Structure and Properties of Nonferrous Alloys. In: Frost B.R.T. (Ed). Material Science and Technology vol. 10B (1994), VCH, Weinheim, Germany Chapter 7
3. I.G. Ritchi, Waterside corrosion of zirconium alloys in nuclear power plants, Tech. Rep. IAEA-TECDOC-996, International Atomic Energy Agency, Vienna, Austria, 1998.
4. Massih A.R., Andersson T., Witt P., Dahlbäck M., and Limbäck M. The effect of quenching rate on the β-to-α phase transformation structure in zirconium alloy. Journal of Nuclear Materials 322 (2003) 138-151
5. Garzarolli F., Stehle H., Steinberg E., and Weidinger H. Progress in the knowledge of nodular corrosion. In: Adamson R., and van Swam L. (Eds). Zirconium in Nuclear Industry: Seventh International Symposium vol. ASTM-STP 939 (1987), American Society for Testing of Materials, Philadelphia, USA 417-430
6. Weidinger H., Garzarolli F., Eucken C.M., and Baroch E.F. Effect of chemistry on elevated temperature nodular corrosion. In: Adamson R., and van Swam L. (Eds). Zirconium in Nuclear Industry: Seventh International Symposium vol. ASTMSTP 939 (1987), American Society for Testing of Materials, Philadelphia, USA 364-386
7. Charquet D. Improvement of the uniform corrosion resistance of Zircaloy-4 in the absence of irradiation. Journal of Nuclear Materials 160 (1988) 186-195
8. Gilbert R.W., Griffiths M., and Carpenter G.J.C. Amorphous intermetallics in neutron irradiated Zircaloys after high fluences. Journal of Nuclear Materials 135 (1985) 265-268
9. Yang W.J.S., Tucker R.P., Cheng B., and Adamson R.B. Precipitates in zircaloy: identification and the effect irradiation and heat treatment. Journal of Nuclear Materials 138 (1986) 185-195
10. Cheng B., Kruger R.M., and Adamson R.B. Corrosion behavior of irradiated Zircaloy. In: Garde A.M., and Bradley E.R. (Eds). Zirconium in Nuclear Industry: Tenth International Symposium vol. ASTM STP 1245 (1994), American Society for Testing of Materials, Philadelphia, USA 400-418
11. Andersson T., Thorvaldsson T., Wilson S.A., and Wardle A.M. Influence of thermal processing and microstructure on the corrosion behavior of Zircaloy-4 tubing. International Symposium on Improvements of Water Reactor Fuel Technology and Utilization (1987), International Atomic Energy Agency, Vienna, Austria 435-449
12. Gros J.F., and Wadier J.F. Precipitate growth kinetics in Zircaloy-4. Journal of Nuclear Materials 172 (1990) 85-96
13. Liu P., Örnhagen C., and Nilsson J.O. A novel method for automatic image analysis of particle size distribution in Zircaloy based on secondary electrons in STEM. Scripta Materialia (1998) 775-781
14. Kass S. Corrosion in Zirconium Alloys vol. STP 368 (1965), American Society for Testing and Materials, Philadelphia, PA 3-27
15. Cox B. Oxidation of zirconium and its alloys. In: Fontana M.G., and Staehle R.W. (Eds). Advances in Corrosion Science and Technology vol. 5 (1976), Plenum, New York 173-391
16. Andersson T., and Vesterlund G. Beta quenching of Zircaloy cladding tubes in intermediate and final size. In: Franklin D.G. (Ed). Zirconium in Nuclear Industry: Fifth International Symposium vol. ASTM STP 754 (1982), American Society for Testing of Materials, Philadelphia, USA 75-95
17. Kuwae R., Sato K., Higashinakagawa E., Kawashima J., and Nakamura S. Mechanism of Zircaloy nodular corrosion. Journal of Nuclear Materials 119 (1983) 229
18. Bangaru N.V., Busch R.A., and Schemel J.H. Effect of beta quenching on the microstructure and corrosion of Zircaloys. In: Adamson R., and van Swam L. (Eds). Zirconium in Nuclear Industry: Seventh International Symposium vol. ASTM STP 939 (1987), American Society for Testing of Materials, Philadelphia, USA 341-363
19. Rudling P., Vannesjö K.L., Vesterlund G., and Massih A.R. The influence of the second phase particles on Zircaloy corrosion in BWR environment. In: Adamson R., and van Swam L. (Eds). Zirconium in Nuclear Industry: Seventh International Symposium vol. ASTM STP 939 (1987), American Society for Testing of Materials, Philadelphia, USA 292-306
20. Cheng B., and Adamson R.B. Mechanistic studies of Zircaloy nodular corrosion,. In: Adamson R., and van Swam L. (Eds). Zirconium in Nuclear Industry: Seventh International Symposium vol. ASTM STP 939 (1987), American Society for Testing of Materials, Philadelphia, USA 387-416
21. Griffiths M., Gilbert R.W., and Carpenter G.J.C. Phase stability, decomposition and redistribution of intermetallic precipitates in Zircaloy-2 and -4 during neutron irradiation. Journal of Nuclear Materials 150 (1987) 53-66
22. Etoh Y., and Shimada S. Neutron irradiation effects on intermetallic precipitates in Zircaloy as a function of fluence. Journal of Nuclear Materials 200 (1993) 59-69
23. Motta A.T., and Lemaignan C. A balistic mixing model for amorphization of precipitates in Zircaloy under neutron irradiation. Journal of Nuclear Materials 195 (1992) 277-285
24. Motta A.T., and Lemaignan C. In: Yavari A.R. (Ed). Ordering and Disordering in Alloys (1992), Elsevier Applied Science, London, UK 255-275
25. Shimada S., Etoh T., and Tomita K. BWR Zircaloy cladding corrosion behavior. Journal of Nuclear Materials 248 (1997) 275-280
26. Tägtström T., Limbäck M., Dahlbäck M., Andersson T., and Pettersson H. Effects of hydrogen pickup and second phase particle dissolution on the in-reactor corrosion performance of BWR claddings. In: Moan G., and Rudling P. (Eds). Zirconium in Nuclear Industry: Thirteenth International Symposium vol. ASTM STP 1423 (2002), American Society for Testing of Materials, W. Conshohocken, PA, USA 96-118
27. Rudling P., Wikmark G., Lehtinen B., and Pettersson H. Impact of second phase particles on BWR Zr-2 claddings. In: Sabol G.P., and Moan G. (Eds). Zirconium in Nuclear Industry: Twelfth International Symposium vol. ASTM STP 1354 (2000), American Society for Testing of Materials, W. Conshohocken, PA, USA 687-706
28. Cottrell A. An introduction to metallurgy (1995), The Institute of Materials, London, England
29. Bradhurst D.H., and Heuer D.H. The influence of oxide stress on the break-away oxidation of Zircaloy-2. Journal of Nuclear Materials (1970) 35-47
30. Ahmed T., and Keys L.H. The break-away oxidation of zirconium and its alloys: a review. Journal of the Less Common Metals 39 (1975) 99-107
31. Inagaki M., Kanno M., and Maki H. Effect of alloying elements in Zircaloy on photoelectrochemical characteristics of zirconium oxide films. In: Eucken C.M., and Garde A.M. (Eds). Zirconium in Nuclear Industry: Ninth International Symposium vol. ASTM STP 1132 (1991), American Society for Testing of Materials, Philadelphia, USA 437-460
32. Nanikawa S., Etoh Y., Shimada S., Kubo T., Ito K., and Harada H. Correlation between characteristics of oxide films formed on Zr alloys in BWRs and corrosion performance. In: Sabol G.P., and Moan G. (Eds). Zirconium in Nuclear Industry: Twelfth International Symposium vol. ASTM STP 1354 (2000), American Society for Testing of Materials, W. Conshohocken, PA, USA 815-835
33. Pêcheur D., Lefebvre F., Motta A.T., and Lemaignan C. Precipitate evolution in the Zircaloy-4 oxide layer. Journal of Nuclear Materials 189 (1992) 318-332
34. Pêcheur D., Lefebvre F., Motta A.T., Lemaignan C., and Charquet D. Oxidation of intermetallic precipitates in Zrircaloy-4: impact of irradiation. In: Garde A.M., and Bradley E.R. (Eds). Zirconium in Nuclear Industry: Tenth International Symposium vol. ASTM STP 1245 (1994), American Society for Testing of Materials, Philadelphia, PA, USA 687-708
35. J. Godlewski, How the tetragonal zirconia is stabilized in the oxide scale that is formed on a zirconium alloy corroded at 400 °C in steam, vol. ASTM STP 1245, 1994, pp. 663-686.
36. Kubo T., and Uno M. Precipitate behavior in Zircaloy-2 oxide films and its relevance to corrosion resistance. In: Eucken C.M., and Garde A.M. (Eds). Zirconium in Nuclear Industry: Ninth International Symposium vol. ASTM STP 1132 (1991), American Society for Testing of Materials, Philadelphia, USA 476-498
37. A.R. Massih, L.O. Jernkvist, Calculation of some microstructural features of Zircaloy-2 plates with different thicknesses under β quenching in Ar gas, Tech. Rep. PM 04-002, Quantum Technologies, 2005.
38. A.R. Massih, L.O. Jernkvist, Calculation of the evolution of microstructure of Zircaloy-2 across a plate during water quenching in space and time, Tech. Rep. PM 04-003, Quantum Technologies, 2005.
39. L.O. Jernkvist, A.R. Massih, Quench 2.0 general description, Tech. Rep. TR 04-007, Quantum Technologies, 2005.
40. Woo O.T., and Tangri K. Transformation characteristics of rapidly heated and quenched Zircaloy-4-oxygen alloys. Journal of Nuclear Materials 79 (1979) 82-94
41. Massih A.R., and Jernkvist L.O. Phase ordering under quenching. Journal of Physics and Chemistry of Solids 65 (2004) 1193-1198