Search Results - "Peregud, M.M."

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  1. 1
    Effect of molybdenum on properties of zirconium components of nuclear reactor core

    Effect of molybdenum on properties of zirconium components of nuclear reactor core by Nikulina, A.V., Konkov, V.F., Peregud, M.M., Vorobev, E.E.

    Published in Nuclear materials and energy (01-01-2018)
    “…•In a structure of binary Zr-Mo alloys and Zr-Nb-Mo alloys a strong and corrosion-resistant phase ZrMo2 appears.•In Zr-Sn-Nb-Fe alloys Mo alloying increases…”
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  2. 2
    Dimensional Stability of the Structural Parts of VVER-1000 FA Made of E-635 Zirconium Alloy

    Dimensional Stability of the Structural Parts of VVER-1000 FA Made of E-635 Zirconium Alloy by Nikulina, A. V., Peregud, M. M., Vorob’ev, E. E., Khokhunova, T. N.

    Published in Atomic energy (New York, N.Y.) (01-02-2018)
    “…The dependence of dimensional changes occurring in the structural parts made of E-635 zirconium alloy on the metallurgical and operational factors as a result…”
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  3. 3
    Analysis of the Effect of the Stress-Strain State of Irradiated Zirconium-Alloy Fuel-Element Cladding on Hydride Orientation

    Analysis of the Effect of the Stress-Strain State of Irradiated Zirconium-Alloy Fuel-Element Cladding on Hydride Orientation by Kulakov, G. V., Vatulin, A. V., Konovalov, Yu. V., Kosaurov, A. A., Peregud, M. M., Korotchenko, E. A., Shishin, V. Yu, Shel’dyakov, A. A.

    Published in Atomic energy (New York, N.Y.) (01-06-2017)
    “…The effect of the stress distribution on the hydride distribution in zirconium cladding of fuel elements with dispersion fuel is analyzed. It is shown that…”
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  4. 4
    Behavior of Modified Zirconium-Alloy Fuel-Element Cladding Under Irradiation

    Behavior of Modified Zirconium-Alloy Fuel-Element Cladding Under Irradiation by Kulakov, G. V., Konovalov, Yu. V., Kosaurov, A. A., Peregud, M. M., Nikulina, A. B., Shishin, V. Yu, Ovchinnikov, V. A., Shel’dyakov, A. A.

    Published in Atomic energy (New York, N.Y.) (01-04-2018)
    “…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…”
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  5. 5
    Experience in Operating Accessory Parts Made of Alloy E-635 in VVER-1000 Fuel Assemblies

    Experience in Operating Accessory Parts Made of Alloy E-635 in VVER-1000 Fuel Assemblies by Novikov, V. V., Peregud, M. M., Shevyakov, A. Yu, Shishov, V. N., Volkova, I. N., Shishkin, A. A.

    Published in Atomic energy (New York, N.Y.) (01-12-2013)
    “…Post-reactor studies of structural elements made of E-635 alloy in VVER-1000 TVSA fuel assemblies have shown that with regard to the operating characteristics…”
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  6. 6
    Irradiation-induced microstructural changes in Zr-1% Sn-1% Nb-0.4% Fe

    Irradiation-induced microstructural changes in Zr-1% Sn-1% Nb-0.4% Fe by Nikulina, A.V., Markelov, V.A., Peregud, M.M., Voevodin, V.N., Panchenko, V.L., Kobylyansky, G.P.

    Published in Journal of nuclear materials (01-11-1996)
    “…The high resistance to nodular corrosion and irradiation-induced creep and growth shown by Zr-1% Sn-1% Nb-0.4% Fe compared with Zircaloy or binary ZrNb alloys…”
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