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Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors pp 409–422Cite as

Electrochemical and Microstructural Characterization of Alloy 600 in Low Pressure H2-Steam

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Part of the book series: The Minerals, Metals & Materials Series ((MMMS))

Abstract

Low pressure superheated H2-steam system has been extensively used in the past years to accelerate the oxidation kinetics while keeping the conditions representative to PWR primary water. One of the most important requirements of this environment is that needs to replicate the Ni/NiO transition. However, despite several studies have been carried out by different research groups in H2-steam environment, there is still some level of uncertainty over the thermodynamic of the oxidation process. In this study, the Ni/NiO transition in hydrogenated steam was investigated via electrochemical potential measurements using a Ni/NiO solid state reference electrode. Furthermore, solution annealed Alloy 600 coupons were exposed to H2-steam at 480 ℃ in order to examine the effect of oxidizing conditions with respect to the Ni/NiO transition on the preferential intergranular oxidation. The effect of the redox potential on the preferential intergranular oxidation is discussed in the context of the precursor stages of stress corrosion cracking for Alloy 600.

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References

  1. P. Scott, M. Le Calvar, Some possible mechanisms of intergranular stress corrosion cracking of Alloy 600 in PWR primary water, in 6th International Conference on Environment Degradation of Materials in Nuclear Power Systems—Water Reactors, pp. 657–667, San Diego, 1993

    Google Scholar 

  2. G. Economy, R.J. Jacko, F.W. Pement, Igscc behavior of alloy 600 steam-generator tubing in water or steam tests above 360 C. Corrosion 43(12), 727–773 (1987)

    Article  CAS  Google Scholar 

  3. F. Scenini, R.C. Newman, R.A. Cottis, R.J. Jacko, Alloy oxidation studies related to PWSCC, in 12th International Conference on Environment Degradation of Materials in Nuclear Power Systems, 2005

    Google Scholar 

  4. G. Bertali, F. Scenini, M.G. Burke, Advanced microstructural characterization of the intergranular oxidation of alloy 600. Corros. Sci. 100, 474–483 (2015)

    Article  CAS  Google Scholar 

  5. G. Bertali, F. Scenini, M.G. Burke, The intergranular oxidation susceptibility of thermally—Treated Alloy. Corros. Sci. 114, 112–122 (2017)

    Article  CAS  Google Scholar 

  6. G. Bertali, F. Scenini, M.G.G. Burke, The effect of residual stress on the preferential intergranular oxidation of alloy 600. Corros. Sci. 111, 494–507 (2016)

    Article  CAS  Google Scholar 

  7. S.Y. Persaud, A. Korinek, J. Huang, G.A. Botton, R.C. Newman, Internal oxidation of alloy 600 exposed to hydrogenated steam and the beneficial effects of thermal treatment. Corros. Sci. 86, 108–122 (2014)

    Article  CAS  Google Scholar 

  8. S.Y. Persaud, R.C. Newman, A.G. Carcea, G.A. Botton, J. Huang, A. Korinek, S. Ramamurthy, Grain boundary embrittlement of alloy 600 by internal oxidation in simulated primary water environments, in 16th International Conference on Environment Degradation of Materials in Nuclear Power Systems—Water Reacter, 2013

    Google Scholar 

  9. D.S. Morton, S.A. Attanasio, G.A. Young, Primary water SCC understanding and characterization through fundamental testing in the vicinity of the Nickel/Nickel oxide phase transition, in 10th International Conference on Environment Degradation of Materials in Nuclear Power Systems—Water Reacter, 2001

    Google Scholar 

  10. L. Lindsay, F. Scenini, X. Zhou, G. Bertali, R.A. Cottis, M.G. Burke, F. Carrette, F. Vaillant, Characterisation of stress corrosion cracking and internal oxidation of alloy 600 in high temperature hydrogenated steam, in 16th International Conference on Environment Degradation of Materials in Nuclear Power Systems—Water Reacter, 2013

    Google Scholar 

  11. A. Molander, 12. On line electrochemical monitoring in light water reactor (LWR) systems, Nucl. Corros. Sci. Eng., pp. 408–437 (2012)

    Google Scholar 

  12. T. Terachi, N. Totsuka, T. Yamada, T. Nakagawa, H. Deguchi, M. Horiuchi, M. Oshitani, Influence of dissolved hydrogen on structure of oxide film on Alloy 600 formed in primary water of pressurized water reactors. J. Nucl. Sci. Technol. 40(7), 509–516 (2003)

    Article  CAS  Google Scholar 

  13. S.A. Attanasio, D.S. Morton, Measurement of the Nickel/Nickel oxide transition in Ni–Cr–Fe Alloys and Updated Data and Correlations to Quantify the Effect of Aqueous Hydrogen on Primary Water SCC, in 11th International Conference on Environment Degradation of Materials in Nuclear Power Systems—Water Reacter, pp. 143–155, 2003

    Google Scholar 

  14. B.M. Capell, G.S. Was, Selective internal oxidation as a mechanism for intergranular stress corrosion cracking of Ni–Cr–Fe alloys. Metall. Mater. Trans. A Phys. Metall Mater. Sci. 38(6), 1244–1259 (2007)

    Article  CAS  Google Scholar 

  15. D.D. Macdonald, 11. Electrochemical techniques for monitoring and controling corrosion in water-cooled nuclear reactor systems, Nucl. Corros. Sci. Eng., pp. 331–407 (2012)

    Google Scholar 

  16. O. Kubaschewski, C.B. Alcock, Metallurgical Thermochemistry 5th Edition Revised and Enlarged

    Google Scholar 

  17. J.W. Cahn, J.D. Pan, R.W. Balluffi, Diffusion indeced grain boundary migration. Scr. Metall. 13(6), 503–509 (1979)

    Article  CAS  Google Scholar 

  18. S. Guruswamy, S.M. Park, J.P. Hirth, R.A. Rapp, Internal oxidation of silver-indium alloys: stress relief and the influence of imposed strain. Oxid. Met. 26(1–2), 77–103 (1986)

    Article  CAS  Google Scholar 

  19. J. Panter, M. Foucault, J.M. Cloue, P. Combrade, B. Viguier, E. Andrieu, Surface layers on alloys 600 and 690 in PWR primary water possible influence on stress corrosion crack initiation, in Specific Technology Group 41—Energy Generation Corrosion; Denver, CO, USA; NACE International

    Google Scholar 

  20. D.S. Morton, N. Lewis, M. Hanson, S. Rice, Paul Sander, Nickel alloy primary water bulk surface and SCC corrosion film analytical characterization and SCC mechanistic implications, in International Conference on Environmental Degradation of Materials in Nuclear Power Systems, Whistler, British Columbia, 2007, pp. 1–16

    Google Scholar 

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Acknowledgements

The authors gratefully acknowledge the Manchester Metallurgical Society and the EPSRC through the NNUMAN programme (EP/JO21172/1) for the financial support and Dr. Peter Andresen for donating the Cu/Cu2O solid state reference electrode that was initially used for preliminary electrochemical experiments.

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Authors and Affiliations

  1. Materials Performance Centre, University of Manchester, Manchester, UK

    L. Volpe, G. Bertali, M. G. Burke & F. Scenini

  2. Corrosion and Protection Centre, The University of Manchester, Manchester, UK

    M. Curioni

Authors
  1. L. Volpe
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  2. G. Bertali
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  3. M. Curioni
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  4. M. G. Burke
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  5. F. Scenini
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Corresponding author

Correspondence to L. Volpe .

Editor information

Editors and Affiliations

  1. Idaho National Laboratory, Idaho Falls, ID, USA

    John H. Jackson

  2. Naval Nuclear Laboratory, Pittsburgh, PA, USA

    Denise Paraventi

  3. Chalk River Laboratories, Canadian Nuclear Laboratories, Chalk River, ON, Canada

    Michael Wright

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© 2019 The Minerals, Metals & Materials Society

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Volpe, L., Bertali, G., Curioni, M., Burke, M.G., Scenini, F. (2019). Electrochemical and Microstructural Characterization of Alloy 600 in Low Pressure H2-Steam. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_26

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