Search Results - "MARANCHAK, S. V"

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  1. 1

    Fuel cycles with advanced dispersion fuel elements of high uranium density by Savchenko, A. M., Karpyuk, L. A., Dergunova, E. A., Konovalov, Yu. V., Kulakov, G. V., Maranchak, S. V., Ershov, S. A., Kupenko, V. I., Mainikov, E. V.

    Published in Atomic energy (New York, N.Y.) (01-07-2023)
    “…The paper considers the possibility of replacing container fuel elements of thermal reactors with uranium dioxide or mixed oxide uranium-plutonium fuel with…”
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    Journal Article
  2. 2

    Testing of Dispersion Type Fuel Rods with a Heat-Proof Meat with Controlled Porosity for Small Nuclear Power Plants by Savchenko, A. M., Konovalov, Yu. V., Kulakov, G. V., Maranchak, S. V., Ershov, S. A., Mainikov, E. V., Kozlov, A. V., Shishin, V. Yu, Sheldyakov, A. A., Yakovlev, V. V.

    Published in Atomic energy (New York, N.Y.) (01-04-2022)
    “…The results of development work on dispersion type fuel rods, whose meat, containing granules of a uranium-molybdenum alloy in a matrix of special zirconium…”
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    Journal Article
  3. 3

    Zirconium alloys matrix as innovative material for composite fuel by Savchenko, A.M., Vatulin, A.V., Morozov, A.V., Kulakov, G.V., Ershov, S.A., Laushkin, A.V., Maranchak, S.V., Konovalov, Y.V., Malamanova, E.K.

    Published in Progress in nuclear energy (New series) (01-05-2012)
    “…A novel class of zirconium alloys is suggested as fuel matrix. They are “deep” ternary or quaternary eutectics having relatively low melting point i.e. from…”
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    Journal Article
  4. 4

    Inert matrix fuel with low melting point zirconium brazing alloys by Savchenko, A.M., Vatulin, A.V., Morozov, A.V., Dobrikova, I.V., Ershov, S.A., Maranchak, S.V., Petrova, Z.N., Konovalov, Y.V.

    Published in Journal of nuclear materials (30-06-2006)
    “…Several versions of inert matrix fuel (IMF) using low melting point zirconium brazing alloys are suggested to improve their utilisation. The alloys are…”
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    Journal Article
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