Hydrothermal deposition of zirconia coatings on pre-oxidized BWR structural materials
Source abstract
Abstract
Abstract An in-situ hydrothermal deposition process was developed to apply a thin film of zirconia (ZrO2) onto structural materials used in Boiling Water Reactors (BWRs) as a potential method for mitigating intergranular stress corrosion cracking (IGSCC). The coating process has been demonstrated to successfully deposit ZrO2 onto as received interior surface of 304 stainless steel and Alloy 600 tubing. 1 This work reports on the application of this coating process to substrates with different surface conditions including the condition that exists on the surface of the structural material in BWRs. The coatings on as-received and pre-oxidized surfaces showed excellent adhesion while those on the polished are usually worse. Tetragonal dominant ZrO2 was found on stainless steel substrates whereas monoclinic/tetragonal mixed ZrO2 was observed on Alloy 600 substrates. The coating on pre-oxidized stainless steel did not reveal a reduced electrochemical potential (ECP) similarly to that was found in our previous study. 1
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Nuclear Materials and Properties · High-Temperature Coating Behaviors
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (21)
Show source-provided references
1. Zhou · Corros. Sci. · 2007 · 49 · 83010.1016/j.corsci.2006.06.019 ↗
2. Y.-J. Kim, P.L. Andresen, in: Eleventh International Conference on Environmental Degradation of Materials in Nuclear Systems, Stevenson, WA, 2003, p. 526.
3. S. Hettiarachchi, G.P. Wozadlo, P.L. Andresen, T.P. Diaz, R.L. Cowan, in: Proceedings of 7th International Symposium on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, NACE, Houston, TX, 1995, p. 735.
4. S. Hettiarachchi, R.J. Law, T.P. Diaz, R.L. Cowan, in: Eighth International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, August 10–14, 1997, p. 535.
5. S. Hettiarachchi, T.P. Diaz, P.L. Andresen, Y.-J. Kim, in: The 3rd International Water Chemistry Conference, San Francisco, 2004, p. 849.
6. D.D. Macdonald, T.K. Yeh, A.T. Motta, Corrosion 95, 1995, Paper No. 403.
7. Y.-J Kim, P.L. Andresen, Corrosion 96, 1996, Paper No. 105.
8. Macdonald · Corrosion · 1992 · 48 · 19410.5006/1.3315925 ↗
9. Macdonald · Corrosion · 1996 · 52 · 76810.5006/1.3292070 ↗
10. Kim · Corrosion · 1998 · 54 · 101210.5006/1.3284814 ↗
11. P.L. Andresen, Y.-J. Kim, US Patent No. 5,465,281.
12. Zhou · Corros. Sci. · 1998 · 40 · 134910.1016/S0010-938X(98)00018-3 ↗
13. Stellwag · Water Chem. Nucl. Reactor Syst. · 2000 · 32 · 127
14. Yeh · J. Nucl. Sci. Technol. · 2002 · 39 · 53110.3327/jnst.39.531 ↗
15. T.-K. Yeh, C.-H. Tsai, C.-H. Chen, C.-M. Cheng, R.-F. Sheng, F. Chu, in: The 3rd International Water Chemistry Conference, San Francisco, 2004, p. 627.
16. Z.F. Zhou, S.N. Lvov, S.S. Thakur, X.Y. Zhou, P. Chou, R. Pathania, in: The 3rd International Water Chemistry Conference, San Francisco, 2004, p. 602.
17. P.L. Andresen, F.P Ford, S.M. Murphy, J.M. Perks, in: Fourth International Conference on Environmental Degradation of Materials in Nuclear Power System – Water Reactors, NACE, Houston, TX, 1990, p. 1/83.
18. R.J. Law, Private communications.
19. Macdonald · Pure Appl. Chem. · 1999 · 71 · 95110.1351/pac199971060951 ↗
20. Mintz · Key Eng. Mater. · 2004 · 261–263 · 87510.4028/www.scientific.net/KEM.261-263.875 ↗
21. Macdonald · Corrosion · 1992 · 48 · 19410.5006/1.3315925 ↗