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Corrosion of zirconium alloys in the superheated steam of a power reactor

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Literature Cited

  1. Corrosion and Protection of Chemical Equipment (Reference Handbook) [in Russian], Vol. 1, Khimiya, Leningrad (1969).

  2. E. E. Fedyushin V. P. Gol'tsev, and V. F. Korotov, in: Report of the All-Union School on Intrareactor Methods of Investigations [in Russian], Dimitrovgrad (1978), p. 169.

  3. Corrosion Resistance of Reactor Materials (Reference Handbook) [in Russian], Atomizdat, Moscow (1976).

  4. E. Tolksdorf, J. Nucl. Mater.,51, No. 3, 330 (1974).

    Google Scholar 

  5. V. G. Parfenov, V. V. Gerasimov, and G. I. Venediktova, Corrosion of Zirconium and Its Alloys [in Russian], Atomizdat, Moscow (1967).

    Google Scholar 

  6. R. Ronald et al., A study of Zircaloy-4—Steam Oxidation. Reaction Kinetics. EPRI NP-225 (Research Project 249-1, September 1976).

  7. A. S. Zaimovskii, At. Energ.,45, No. 6, 430 (1978).

    Google Scholar 

  8. M. G. Golovachev, At. Energ.,42, No. 5, 409 (1977).

    Google Scholar 

  9. V. Urbanic, The Effect of Aging on the Corrosion of Zr+2.5% Nb. Presented at the NASA National Meeting, California, March 19–23, 1973.

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Translated from Atomnaya Énergiya, Vol. 54, No. 2, pp. 114–116, February, 1983.

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Samsonov, B.V., Seredkin, S.V., Shulimov, V.N. et al. Corrosion of zirconium alloys in the superheated steam of a power reactor. At Energy 54, 124–127 (1983). https://doi.org/10.1007/BF01123293

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  • DOI: https://doi.org/10.1007/BF01123293

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