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N-1 alloy creep at 1170–1370 K

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Literature Cited

  1. A. S. Zaimovskii, A. N. Nikulina, and N. G. Reshetnikov, Zirconium Alloys in Nuclear Engineering [in Russian], Énergoatomizdat, Moscow (1981).

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  2. H. Evans and G. Knowles, “On the creep characteristics of β-zircalloy,” J. Nucl. Mat.,78, No. 1, 43–48 (1978).

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  3. H. Rosinger, P. Bera, and W. Clendening, “Steady-state creep of zircalloy-4 fuel cladding from 940 to 1873 K,” ibid.,82, No. 2, 286–297 (1979).

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  4. G. B. Fedorov and E. A. Smirnov, Diffusion in Reactor Materials [in Russian], Atomizdat, Moscow (1978).

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Authors
  1. M. I. Alymov
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  2. E. N. Pirogov
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  3. L. L. Artyukhina
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  4. O. V. Komarov
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Translated from Atomnaya Énergiya, Vol. 65, No. 3, p. 227, September, 1988.

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Alymov, M.I., Pirogov, E.N., Artyukhina, L.L. et al. N-1 alloy creep at 1170–1370 K. At Energy 65, 791–792 (1988). https://doi.org/10.1007/BF01123027

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  • DOI: https://doi.org/10.1007/BF01123027

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