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Oxidation of Zirconium Alloys in Oxygen at High Temperatures up to 1600 °C

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Abstract

The oxidation kinetics of the classic pressurized water reactors (PWR) cladding alloy Zircaloy-4 has been extensively investigated over a wide temperature range. In recent years, new cladding alloys optimized for longer operation and higher burn-up are being increasingly used in Western light water reactors (LWR). These alloys were naturally optimized regarding their corrosion behavior for operational conditions. The publicly available data on high temperature oxidation of the various cladding materials are very scarce. This paper presents the results of a first test series with Zircaloy-4 as reference material, Framatome Duplex cladding, Framatome M5® and the Russian E110 alloy. The first two are Zr–Sn, the latter two Zr–Nb alloys. All materials were investigated in isothermal and transient tests in a thermal balance under argon–oxygen atmosphere. Strong and varying differences (up to 500%) of oxidation kinetics between the alloys were found till 1000 °C, where the breakaway effect plays a role. Smaller but still significant differences (20–30%) were observed at higher temperatures. Generally, the advanced cladding alloys here studied show also a favorable behavior at high temperatures during accident scenarios.

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References

  1. B. Cox, Journal of Nuclear Materials 336, 331 (2005).

    Article  CAS  Google Scholar 

  2. G. Schanz, B. Adroguer and A. Volchek, Nuclear Engineering and Design 232, 75 (2004).

    Article  CAS  Google Scholar 

  3. L. Sepold, M. Grosse, M. Steinbrück, and J. Stuckert, in 16 th International Conference on Nuclear Engineering, May 11–15, 2008, Orlando, FL, USA, paper ICONE16-48074.

  4. M. Grosse, in Proceedings of the Annual Meeting on Nuclear Technology, Karlsruhe, May 22–24, 2007, p. 285.

  5. J. Stuckert, M. Steinbrück, and U. Stegmaier, Report FZKA-6604, Forschungszentrum Karlsruhe, 2001.

  6. G. Schanz, Report FZKA-7329, Forschungszentrum Karlsruhe, 2007.

  7. M. Grosse, in Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP ‘08), June 8–12, 2008, Anaheim, CA, USA.

  8. J. B. Abriata, J. Garces, and R. Versaci, Bulletin Alloy of Phase Diagrams 7, 116 (1986).

    Article  CAS  Google Scholar 

  9. N. Birks, G. H. Meier, and F. S. Pettit, Introduction to the High-Temperature Oxidation of Metals, 2nd edn. (Cambridge University Press, 2006), ISBN 978-0-521-48042-0.

  10. L. Baker and L. C. Just, Technical Report ANL-6548, Argonne National Laboratory, 1962.

  11. J. V. Cathcart, R. E. Pawel, R. A. McKee, R. E. Druschel, G. J. Yurek, J. J. Campbell, and S. H. Jury, Technical Report ORNL/NUREG-17, 1977.

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Acknowledgments

This work was sponsored by the HGF Program NUKLEAR at Forschungszentrum Karlsruhe. The author is very grateful to G. Schanz and M. Grosse (FZK) for many fruitful discussions and to J. Birchley (PSI) for the critical review of the paper. Sample preparation and microscopic examinations were performed by P. Severloh and U. Stegmaier (FZK). The Zr1Nb (E110) was provided by Russian institutions in the context of the EU program ISTC 1648.2. M5 and Duplex-D4 rod cladding was delivered by AREVA.

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  1. Forschungszentrum Karlsruhe GmbH, Institut für Materialforschung I, P.O. Box 3640, 76021, Karlsruhe, Germany

    Martin Steinbrück

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  1. Martin Steinbrück
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Correspondence to Martin Steinbrück.

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Steinbrück, M. Oxidation of Zirconium Alloys in Oxygen at High Temperatures up to 1600 °C. Oxid Met 70, 317–329 (2008). https://doi.org/10.1007/s11085-008-9124-z

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  • DOI: https://doi.org/10.1007/s11085-008-9124-z

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