journal article·2012-12

How the crystallography and nanoscale chemistry of the metal/oxide interface develops during the aqueous oxidation of zirconium cladding alloys

N. Ni, D. Hudson, J. Wei, P. Wang, S. Lozano-Perez, G.D.W. Smith, J.M. Sykes, S.S. Yardley, K.L. Moore, S. Lyon, R. Cottis, M. Preuss, C.R.M. Grovenor

Acta Materialia· Volume 60· Issue 20
Publisher page

Abstract

Aqueous corrosion and hydrogenation have become major limiting factors to the use of zirconium alloys as fuel cladding and assembly components in water-cooled nuclear reactors. The metal-oxide interface has been a particular focus of previous research, but there is still no clear understanding of what is present at the interface at different stages of the complex oxidation process. We report here a systematic investigation using state-of-the-art instrumentation on the interfaces in several zirconium alloys corroded for different times. We have shown that thin intermediate oxide layers with compositions close to ZrO can be observed in almost all the pre-transition samples studied, and that this layer thickens during the pre-transition stage. Just before the kinetic transition, a large variation in the suboxide width was detected, suggesting that the kinetic transition is an extremely local process. After transition the suboxide was generally absent. In the suboxide locations different structures, including an unidentified phase, were found. The oxygen-saturated (∼30 at.% O) metal regions found beneath the oxide are thickest in the (late) pre-transition samples and significantly thinner in the post-transition samples. We suggest that the suboxide cannot by itself act as a protective layer and conclude that it is the development of interlinked porosity down to the metal-oxide interface that is the reason for the transition in oxidation kinetics. © 2012 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Fusion materials and technologies

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References (92)

Show source-provided references
1. Cox · J Nucl Mater · 2005 · 336 · 33110.1016/j.jnucmat.2004.09.029 ↗
2. Sabol GP. ZIRLO™—An alloy development success. In: Rudling P, Kammenzind B, editors. Zirconium in the nuclear industry: fourteenth international symposium, ASTM STP 1467. West Conshohocken, PA: ASTM International; 2005.10.1520/STP37500S ↗
3. Oxidation of zirconium and its alloys
4. Pickman DO. Zirconium alloy performance in light water reactors: a review of UK and Scandinavian experience. In: Garde AM, Bradley ER, editors. Zirconium in the nuclear industry: tenth international symposium, ASTM STP 1245. West Conshohocken, PA: ASTM International; 1994.10.1520/STP15182S ↗
5. Nikulina · Met Sci Heat Treat · 2003 · 45 · 28710.1023/A:1027388503837 ↗
6. Lustman · 1955
7. Examinations of the corrosion mechanism of zirconium alloys
8. Kofstad · 1966
9. Lemaignan C. ASM handbook 2006; 13C corrosion: environments and industries; 2006. p. 415.
10. Ahmed · J Less-Common Met · 1975 · 39 · 9910.1016/0022-5088(75)90220-9 ↗
11. Park · J Nucl Mater · 2010 · 399 · 20810.1016/j.jnucmat.2010.01.021 ↗
12. Yoo · J Nucl Mater · 2001 · 299 · 23510.1016/S0022-3115(01)00695-X ↗
13. Ploc · J Nucl Mater · 1980 · 91 · 32210.1016/0022-3115(80)90232-9 ↗
14. Natesan K, Soppet WK. Hydrogen effects on air oxidation of zirlo alloy. Argonne National Laboratory reports ANL-04/14; 2004.
15. Zreiba NA, Northwood DO. J Mater Eng 1985;7.
16. Leistikow · Mater Corros · 1985 · 36 · 10510.1002/maco.19850360302 ↗
17. Baek · J Nucl Mater · 2008 · 372 · 15210.1016/j.jnucmat.2007.02.011 ↗
18. Steinbruck · Prog Nucl Energy · 2010 · 52 · 1910.1016/j.pnucene.2009.07.012 ↗
19. Griggs · J Electrochem Soc · 1962 · 109 · 66510.1149/1.2425526 ↗
20. Maroto · J Nucl Mater · 1996 · 229 · 7910.1016/0022-3115(95)00233-2 ↗
21. Dawson · J Nucl Mater · 1968 · 25 · 17910.1016/0022-3115(68)90044-5 ↗
22. Barberis · J Nucl Mater · 1995 · 226 · 3410.1016/0022-3115(95)00108-5 ↗
23. Park · J Nucl Mater · 2006 · 359 · 5910.1016/j.jnucmat.2006.07.017 ↗
24. Microstructure and growth mechanism of oxide layers formed on Zr alloys studied with micro-beam synchrotron radiation
25. Park · J Alloys Compd · 2007 · 437 · 27410.1016/j.jallcom.2006.07.101 ↗
26. Versaci · J Nucl Mater · 1979 · 80 · 18010.1016/0022-3115(79)90234-4 ↗
27. Yilmazbayhan · J Nucl Mater · 2006 · 349 · 26510.1016/j.jnucmat.2005.10.012 ↗
28. Yilmazbayhan · J Nucl Mater · 2004 · 324 · 610.1016/j.jnucmat.2003.08.038 ↗
29. Long-term in situ corrosion investigation of Zr alloys in simulated PWR environment by electrochemical measurements
30. Ni · Corros Sci · 2011 · 53 · 407310.1016/j.corsci.2011.08.013 ↗
31. Oskarsson · J Nucl Mater · 2001 · 289 · 31510.1016/S0022-3115(01)00416-0 ↗
32. Ishii · Mater High Temp · 2000 · 17 · 2310.1179/mht.2000.005 ↗
33. Yao · J Nucl Mater · 2008 · 374 · 19710.1016/j.jnucmat.2007.08.002 ↗
34. Microstructure of oxide films formed during the waterside corrosion of the Zircaloy-4 cladding in lithiated environment
35. Oxide growth mechanism on zirconium alloys
36. Anada H, Takeda K. Microstructure of oxides on Zircaloy-4, 1.0Nb Zircaloy-4, and Zircaloy-2 formed in 10.3-MPa steam at 673 K. In: Bradley ER, Sabol GP, editors. Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295. West Conshohocken, PA: ASTM International; 1996.10.1520/STP16166S ↗
37. The microstructural characterization of factors which determin the degradation behaviour of Zircaloy-4
38. Wadman · J Nucl Mater · 1993 · 200 · 20710.1016/0022-3115(93)90331-R ↗
39. Oskarsson · J Nucl Mater · 2001 · 297 · 7710.1016/S0022-3115(01)00580-3 ↗
40. Kim · J Nucl Mater · 2008 · 374 · 20410.1016/j.jnucmat.2007.08.003 ↗
41. Hsieh · Mater Chem Phys · 1997 · 50 · 3710.1016/S0254-0584(97)80181-2 ↗
42. Comparison of the high burn-up corrosion on M5 and low tin Zircaloy-4
43. Jeong · J Nucl Mater · 1999 · 270 · 32210.1016/S0022-3115(99)00008-2 ↗
44. TEM examinations of the metal-oxide interface of zirconium based alloys irradiated in a pressurized water reactor
45. Microstructure of oxide layers formed during autoclave testing of zirconium alloys, ASTM STP 1245
46. Park · J Nucl Mater · 2004 · 335 · 43310.1016/j.jnucmat.2004.07.051 ↗
47. Effect of annealing temperature on corrosion behavior and ZrO2 microstructure of Zircaloy-4 cladding tube
48. Roy · J Nucl Mater · 1970 · 37 · 7110.1016/0022-3115(70)90183-2 ↗
49. Pemsler · Electrochem Technol · 1966 · 4 · 128
50. Zhang · J Nucl Mater · 2010 · 396 · 6510.1016/j.jnucmat.2009.10.055 ↗
51. Raman spectroscopy study of the tetragonal-to-monoclinic transition in zirconium oxide scales and determination of overall oxygen diffusion by nuclear microanalysis of O18
52. Arashi · Phys Status Solidi A Appl Res · 1982 · 71 · 31310.1002/pssa.2210710203 ↗
53. How the tetragonal zirconia is stabilized in the oxide scale that if formed on a zirconium alloy corroded at 400°C in steam
54. Multi-scale characterization of the metal-oxide interface of zirconium alloys
55. Precipitate behavior in Zircaloy-2 oxide-films and its relevance to corrosion-resistance
56. Ni · Scripta Mater · 2010 · 62 · 56410.1016/j.scriptamat.2009.12.043 ↗
57. Cox · J Nucl Mater · 1968 · 27 · 110.1016/0022-3115(68)90002-0 ↗
58. Cox · J Nucl Mater · 1994 · 210 · 30310.1016/0022-3115(94)90184-8 ↗
59. Gebhardt · J Nucl Mater · 1993 · 203 · 1710.1016/0022-3115(93)90425-X ↗
60. Gebhardt · Electrochim Acta · 1993 · 38 · 63310.1016/0013-4686(93)80231-N ↗
61. Vermoyal · Electrochim Acta · 1999 · 45 · 103910.1016/S0013-4686(99)00307-2 ↗
62. Warr BD, Heide PAWVD, Maruire MA. Oxide characteristics and corrosion and hydrogen uptake in Zr-2.5 Nb CANDU pressure tubes. In: Bradley ER, Sabol GP, editors. Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295. West Conshohocken, PA: ASTM International; 1996.10.1520/STP16177S ↗
63. The importance of oxide morphology for the oxidation rate of zirconium alloys
64. Investigation of in-pile grown corrosion films on zirconium-based alloys
65. Iltis · J Alloys Compd · 1991 · 177 · 7110.1016/0925-8388(91)90057-3 ↗
66. Takeda · J Nucl Sci Technol · 2006 · 43 · 98410.1080/18811248.2006.9711186 ↗
67. Bohmert · Nucl Eng Des · 1994 · 147 · 5310.1016/0029-5493(94)90256-9 ↗
68. Oxide characteristics and their relationship to hydrogen uptake in zirconium alloys
69. Abolhassani · J Nucl Mater · 2010 · 399 · 110.1016/j.jnucmat.2009.10.060 ↗
70. Instabilities in the oxidation behaviour of Zircaloy-4
71. Furuta · J Nucl Mater · 1980 · 95 · 30310.1016/0022-3115(80)90372-4 ↗
72. Moseley · J Nucl Mater · 1981 · 99 · 34010.1016/0022-3115(81)90206-3 ↗
73. Ni · Ultramicroscopy · 2010 · 111 · 12310.1016/j.ultramic.2010.10.020 ↗
74. Hudson · Scripta Mater · 2009 · 61 · 41110.1016/j.scriptamat.2009.04.032 ↗
75. Hudson · Ultramicroscopy · 2009 · 109 · 66710.1016/j.ultramic.2008.10.020 ↗
76. Foster · 1991
77. Foster JP, Worcester SA, Comstock RJ. Processing zirconium alloy used in light water reactors for specified creep rate. Pittsburgh, PA: Westinghouse Electric Corp.; 1991.
78. Foster · 1992
79. Corrosion behaviour of Zircaloy-4 sheets produced under various hot-rolling and annealing conditions
80. Mayer · MRS Bull · 2007 · 32 · 40010.1557/mrs2007.63 ↗
81. Lozano-Perez · Micron · 2008 · 39 · 32010.1016/j.micron.2007.12.003 ↗
82. Miller · Ultramicroscopy · 2005 · 102 · 28710.1016/j.ultramic.2004.10.011 ↗
83. Hudson D. Zirconium oxidation on the atomic scale. PhD thesis. Department of Materials, University of Oxford; 2011.
84. Banerjee · 2007
85. Li · Mater Sci Eng A Struct Mater · 2004 · 366 · 16410.1016/S0921-5093(02)00787-6 ↗
86. Schefold · J Electrochem Soc · 2003 · 150 · B45110.1149/1.1602079 ↗
87. Yurek · Oxid Met · 1974 · 8 · 26510.1007/BF00609944 ↗
88. Tupin · J Nucl Mater · 2003 · 317 · 13010.1016/S0022-3115(02)01704-X ↗
89. Xia · Phys Rev Lett · 1990 · 64 · 20410.1103/PhysRevLett.64.204 ↗
90. Preuss M, Frankel P, Lozano-Perez S, Hudson D, Polatidis E, Ni N, et al. Towards a mechanistic understanding of corrosion mechanisms in zirconium alloys. In: 16th International symposium on zirconium in the nuclear industry, Chongqing, China. American Society for Testing and Materials; 2010.10.1520/STP49376T ↗
91. Parise · J Nucl Mater · 1998 · 256 · 3510.1016/S0022-3115(98)00045-2 ↗
92. Sikka · Prog Mater Sci · 1982 · 27 · 24510.1016/0079-6425(82)90002-0 ↗