Search Results - Bespechalov, B N

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  1. 1
    Preparation for reactor tests of uranium-zirconium carbonitride fuel

    Preparation for reactor tests of uranium-zirconium carbonitride fuel by Bakhin, A N, Bazyuk, S S, Vishnevsky, V Yu, Repnikov, V M, Kotov, A Yu, Kiselev, D S, Zaitsev, D A, Bespechalov, B N, Titkova, E M, Stoykov, K V, Garmay, Yu V

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  2. 2
    Substantiation of using uranium-zirconium carbonitride as kernel for microspherical fuel

    Substantiation of using uranium-zirconium carbonitride as kernel for microspherical fuel by Bakhin, A N, Bespechalov, B N, Vishnevsky, V Yu, Zaitsev, D A, Kiselev, D S, Kozlov, V V, Kotov, A Yu, Marushkin, D V, Repnikov, V M

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  3. 3
    Interaction of Uranium-Zirconium Carbonitride Fuel Composition with Refractory Structural Materials

    Interaction of Uranium-Zirconium Carbonitride Fuel Composition with Refractory Structural Materials by Zaytsev, D A, Bakhin, A N, Bespechalov, B N, Vishnevsky, V Yu, Kiselev, D S, Kolesnikov, E G, Kotov, A Yu, Kochnov, V Yu, Repnikov, V M, Serikov, V S

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    Azimuthal Deformation Particulars of Single-Crystal Cladding of High-Temperature Fuel Elements

    Azimuthal Deformation Particulars of Single-Crystal Cladding of High-Temperature Fuel Elements by Yastrebkov, A. A., Vybyvanets, V. I., Bespechalov, B. N.

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