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Behavior of Modified Zirconium-Alloy Fuel-Element Cladding Under Irradiation

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Atomic Energy Aims and scope

The first reactor tests and post-reactor studies of fuel elements with cladding made from the zirconium alloys E-636M, E-635opt, and E-635M1, developed at VNIINM, have been conducted. The purpose of the studies was to search for alloys of the type E-635 that surpass the base alloy in terms of resistance to corrosion and hydration. The studies make it possible to recommend the alloys E-635M and E-635opt for use as cladding of the fuel elements in extended-life cores.

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Authors and Affiliations

  1. Bochvar High-Technology Research Institute for Inorganic Materials (VNIINM), Moscow, Russia

    G. V. Kulakov, Yu. V. Konovalov, A. A. Kosaurov, M. M. Peregud & A. B. Nikulina

  2. State Science Center – Research Institute for Atomic Reactors (GNTs NIIAR), Dimitrovgrad, Russia

    V. Yu. Shishin, V. A. Ovchinnikov & A. A. Shel’dyakov

Authors
  1. G. V. Kulakov
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  2. Yu. V. Konovalov
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  3. A. A. Kosaurov
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  4. M. M. Peregud
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  5. A. B. Nikulina
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  6. V. Yu. Shishin
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  7. V. A. Ovchinnikov
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  8. A. A. Shel’dyakov
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Additional information

Translated from Atomnaya Énergiya, Vol. 123, No. 6, pp. 329–334, December, 2017.

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Kulakov, G.V., Konovalov, Y.V., Kosaurov, A.A. et al. Behavior of Modified Zirconium-Alloy Fuel-Element Cladding Under Irradiation. At Energy 123, 399–405 (2018). https://doi.org/10.1007/s10512-018-0359-8

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  • DOI: https://doi.org/10.1007/s10512-018-0359-8

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