Oxidation of Metals

, Volume 89, Issue 1–2, pp 151–163 | Cite as

Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water

  • Suzan Bsat
  • Bingjie Xiao
  • Xiao Huang
  • Sami Penttilä
Original Paper


The choice of materials is of great concern in the construction of Gen IV supercritical water-cooled reactors (SCWRs), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. Material’s performance under simulated conditions must be evaluated to support proper material selection by designers. In this study, alloys 800H, 3003 and 304 were tested in SCW at 700 °C and 25 MPa for 1000 h. The results showed that only alloy 3033 experienced weight gain while weight loss was found for alloys 304 and 800H. Based on SEM/EDS and XRD analyses, spinel and Cr2O3, in addition to small amount of Fe2O3, formed on 800H surface, while predominant Cr2O3 and some spinel were present on alloy 3033. Alloy 304 showed no evidence of Cr2O3 on the surface, although some Cr-containing spinel and Fe2O3 were detected on the surface.


Oxidation Alloy 800H Alloy 3033 Alloy 304 Supercritical water-cooled reactor (SCWR) Weight change Surface oxide SEM XRD 



Funding to the Canada Gen IV National Program was provided by Natural Resources Canada through the Office of Energy Research and Development, Atomic Energy of Canada Limited and Natural Sciences and Engineering Research Council of Canada.


  1. 1.
    World population to 2300, United Nations Department of Economic and Social, New York, 2004.Google Scholar
  2. 2.
    Nuclear Energy Research Advisory Committee and Gen IV International Forum, DOE, US, 2002.Google Scholar
  3. 3.
    T. Schulenberg, H. Matsui, L. Leung and A. Sedov, Supercritical water cooled reactors, in GIF Symposium Proceedings and 2012 Annual Report, San Diego, 2012.Google Scholar
  4. 4.
    M. Yetisir, M. Gaudet and D. Rhodes, Development and integration of Canadian SCWR concept with counter-flow fuel assembly, in ISSCWR-6, Shenzhen, 2013.Google Scholar
  5. 5.
    R. Klueh, Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors, Int Mat Rev 50, 287–310 (2005).CrossRefGoogle Scholar
  6. 6.
    S. Briefing, Nickel-based super alloys, in INSG Insight, 2003.Google Scholar
  7. 7.
    L. Zhang, F. Zhu, Y. Bao and R. Tang, Corrosion tests of candidate fuel cladding and reactor internal structural materials, in 2nd Canada-China joint workshop on ‘Supercritical water-cooled reactors’, Toronto, 2010.Google Scholar
  8. 8.
    T. Allen, Y. Chen, X. Ren, K. Sridhara, L. Tan, G. Was, E. West, and D. Guzonas, in Material Performances in Supercritical Water. Comprehensive Nuclear Materials, (Elsevier, Amsterdam, 2012), pp. 279–326.CrossRefGoogle Scholar
  9. 9.
    L. Greenwood, A new calculation of thermal neutron damage and helium production in nickel. J Nucl Mat 115, 137–142 (1983).CrossRefGoogle Scholar
  10. 10.
    G. Was, P. Ampornrat, G. Gupta, S. Teysseyre, E. West, T. Allen, K. Sridharan, L. Tan, Y. Chen, X. Ren and C. Pister, Corrosion and stress corrosion cracking in supercritical water. J Nucl Mater 371, 176–201 (2007).CrossRefGoogle Scholar
  11. 11.
    K. Ehrlich, J. Konys and L. Heikinheimo, Materials for high performance light water reactor. J Nucl Mater 327, 140–147 (2004).CrossRefGoogle Scholar
  12. 12.
    K. Murty and I. Charit, Structural materials for Gen-IV nuclear reactor: challlenges and opportunities. J Nucl Mater 383, 189–195 (2008).CrossRefGoogle Scholar
  13. 13.
    Y. Nakazono, T. Iwai and H. Abe, General corrosion properties of modified PNC1520 austenitic stainless steel in supercritical water as fuel cladding candidate material for supercritical water reactor. J Phy Conf Ser 215, 012094 (2010).CrossRefGoogle Scholar
  14. 14.
    R. Peraldi and B. Pint, Effect of Ni and Cr contents on the oxidation behaviour of ferritic and austenitic model alloys in air with water vapor. Oxidation of Metals 61, 463–483 (2004).CrossRefGoogle Scholar
  15. 15.
    W. Callister, Materials science and engineering an introduction, (John Wiley & Sons Inc., New York, 2007).Google Scholar
  16. 16.
    A. Fry, S. Osgerby and M. Wright, Oxidation of alloys in steam envrironments- a review. National Physical Laboratory Report MATC 90, 1–39 (2002).Google Scholar
  17. 17.
    Y. Otoguro, M. Sakakibara, T. Saito, H. Ito and Y. Inoue, Oxidation behaviour of austenitic heat-resisting steels in a high temperature and high pressure steam environment. Trans Iron Steel Inst Japan 28, 761–768 (1988).CrossRefGoogle Scholar
  18. 18.
    S. Bsat and X. Huang, Corrosion behaviour of alloy 800H in low density superheated steam. ISIJ Int 56, 1067–1075 (2016).CrossRefGoogle Scholar
  19. 19.
    Sand Meyer Steel Company, Specification sheet: Alloy 800H/800HT, [Online]. Available: [Accessed May 2016].
  20. 20.
    Nickel Development Institute, High temperature characteristics of stainless steels, [Online]. Available: [Accessed May 2016].
  21. 21.
    VDM Metals, VDM Alloy 33 Nicrofer 33, [Online]. Available: [Accessed May 2016].
  22. 22.
    S. Saunders, The oxidation behaviour of metals and alloys at high temperatures in atmospheres containing water vapour: A review. Prog Mat Sci 53, 775–837 (2008).CrossRefGoogle Scholar
  23. 23.
    T. Allen, K. Sridharan, Y. Chen, L. Tan, X. Ren and A. Kruizenga, Research and Development on Materials Corrosion Issues in Supercritical Water Environment, in ICPWS XV, Berlin, 2008.Google Scholar
  24. 24.
    L. Tan, R. X, K. Sridharan and T. Allen, Corrosion behaviour of Ni-base alloys for advanced high temperature water-cooled nuclear reactions, Corr Sci, vol. 50, pp. 3056–3062, 2008.Google Scholar
  25. 25.
    S. Penttila, Private communication. Google Scholar
  26. 26.
    J. Rezek, I. Klein and J. Yahalom, Structure and Corrosion Resistance of Oxide Grown on Maraging Steel in Steam at Elevated Temperatures. App Surf Sci 108, 159–165 (1997).CrossRefGoogle Scholar
  27. 27.
    T. Allen, Y. Chen, L. Tan, X. Ren and K. Sridharan, Corrosion of Candidate Materials for Supercritical Water-Cooled Reactors, in 12th International Conference on Environmental Degradation of Materials in Nuclear Power SystemWater Reactors, Warrendale, 2005.Google Scholar
  28. 28.
    M. Fulger, D. Ohai, M. Mihalache, M. Pantiru and V. Malinovchi, Oxidation Behaviour of Incoloy 800 Under Simulated Supercritical Water Conditions. J Nucl Mat 385, 288–293 (2009).CrossRefGoogle Scholar
  29. 29.
    B. A. Pint, K. A. Terrani, M. P. Brady, T. Cheng and J. R. Keiser, High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments. Journal of nuclear materials 440, (1), 420–427 (2013).CrossRefGoogle Scholar
  30. 30.
    S. Mahboubi, G. Botton and J. Kish, Technical Note: Corrosion Resistance of Alloy 33 (Fe-33Cr-32Ni) in Supercritical Water. Corrosion 71, 1064–1070 (2015).CrossRefGoogle Scholar
  31. 31.
    X. Luo, R. Tang, C. Long, Z. Miao, Q. Peng and C. Li, Corrosion behavior of austenitic and ferritic steels in supercritical water. Nucl Eng Tech 40, 147–154 (2007).CrossRefGoogle Scholar
  32. 32.
    G. Was, S. Teysseyre and Z. Jiao, Corrosion of Austenitic Alloys in Supercritical Water. Corrosion 62, 989–1005 (2006).CrossRefGoogle Scholar
  33. 33.
    D. Rodriguez, A. Merwin and D. Chidambaram, On the oxidation of stainless steel alloy 304 in subcritical and supercritical water. J Nucl Mat 452, 440–445 (2014).CrossRefGoogle Scholar
  34. 34.
    S. F. Li and et al., Corrosion Behaviour of a 304-Oxide Dispersion Strengthened Austenitic Stainless Steel in Supercritical Water, Materials and Corrosion, vol. 67, no. 3, pp. 264–270, 2016.Google Scholar
  35. 35.
    G. H. Meier, A Review of Advances in High Tmeperature Corrosion. Materials Science and Engineering A120–121, 1–11 (1989).Google Scholar
  36. 36.
    R. M. Deacon, Investigation of Corrosion Resistance of Candidate Overlay Alloys in High Temperature Low Nox Environment, (Lehigh University, Thesis, 2004).Google Scholar
  37. 37.
    X. Huang, J. Li and D. Guzonas, Characterization of FeCrAlY Alloy in Supercritical Water. Corrosion Engineering Science and Technology 50, (2), 137–148 (2015).CrossRefGoogle Scholar

Copyright information

© Springer Science+Business Media, LLC 2017

Authors and Affiliations

  • Suzan Bsat
    • 1
  • Bingjie Xiao
    • 1
  • Xiao Huang
    • 1
  • Sami Penttilä
    • 2
  1. 1.Carleton UniversityOttawaCanada
  2. 2.VTT Technical Research Centre of Finland Ltd.EspooFinland

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