Search Results - "Sulatsky, A. A."

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  1. 1

    Self-Similarity in the Problem of Laminar Film Boiling on a Vertical Surface Submerged in a Large Volume of a Liquid by Khabensky, V. B., Sulatsky, A. A.

    Published in Technical physics (01-03-2021)
    “…Using the methods of self-similarity for a laminar free-convective film boiling on a vertical finite-length surface submerged into a large volume of an…”
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    Journal Article
  2. 2

    Experimental Investigation of the High-Temperature Interaction of Steel with a Lead Coolant by Almjashev, V. I., Khabensky, V. B., Krushinov, E. V., Vitol, S. A., Kotova, S. Yu, Shevchenko, E. V., Kalyago, E. K., Sulatsky, A. A., Strizhov, V. F., Mosunova, N. A.

    Published in High temperature (01-12-2022)
    “…This article presents the results of a study of the high-temperature interaction of a lead coolant with the material of the fuel element cladding of the…”
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  3. 3

    Interaction of a Metal Melt of Two-Liquid Corium and Reactor Vessel Steel by Sulatsky, A. A., Khabensky, V. B., Almjashev, V. I., Granovsky, V. S., Krushinov, E. V., Vitol, S. A., Kotova, S. Yu, Shevchenko, E. V., Kalyago, E. K., Raba, B. O., Sulatskaya, M. B.

    Published in High temperature (01-09-2019)
    “…The interaction between a metal melt of two-liquid metal-oxide corium and reactor vessel steel has been experimentally studied as applied to the problem of…”
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  4. 4

    Oxidation effect on steel corrosion and thermal loads during corium melt in-vessel retention by Granovsky, V.S., Khabensky, V.B., Krushinov, E.V., Vitol, S.A., Sulatsky, A.A., Almjashev, V.I., Bechta, S.V., Gusarov, V.V., Barrachin, M., Bottomley, P.D., Fischer, M., Piluso, P.

    Published in Nuclear engineering and design (15-10-2014)
    “…•The METCOR facility simulates vessel steel corrosion in contact with corium.•Steel corrosion rates in UO2+x–ZrO2–FeOy coria accelerate above 1050K.•However…”
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  5. 5

    Experimental study of transient phenomena in the three-liquid oxidic-metallic corium pool by Almjashev, V.I., Granovsky, V.S., Khabensky, V.B., Kotova, S.Yu, Krushinov, E.V., Sulatsky, A.A., Vitol, S.A., Gusarov, V.V., Fichot, F., Michel, B., Piluso, P., Le Tellier, R., Fischer, M., Le Guennic, C., Bakouta, N.

    Published in Nuclear engineering and design (01-06-2018)
    “…•Physicochemical phenomena in 3-liquid corium pool are studied under IVR conditions.•3-liquid pool structure can stay stable for a certain period of…”
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  6. 6

    Oxidation kinetics of corium pool by Sulatsky, A.A., Smirnov, S.A., Granovsky, V.S., Khabensky, V.B., Krushinov, E.V., Vitol, S.A., Kotova, S.Yu, Fischer, M., Hellmann, S., Tromm, W., Miassoedov, A., Bottomley, D., Piluso, P., Barrachin, M.

    Published in Nuclear engineering and design (01-09-2013)
    “…•The analysis of experimental data on molten corium oxidation was been carried out.•The analysis has revealed the main factors influencing the oxidation…”
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  7. 7

    Effect of temperature gradient on chemical element partitioning in corium pool during in-vessel retention by Khabensky, V.B., Granovsky, V.S., Almjashev, V.I., Vitol, S.A., Krushinov, E.V., Kotova, S.Ju, Sulatsky, A.A., Gusarov, V.V., Bechta, S.V., Barrachin, M., Bottomley, D., Fischer, M., Hellmann, S., Piluso, P., Miassoedov, A., Tromm, W.

    Published in Nuclear engineering and design (01-02-2018)
    “…•Simple equations for temperature gradients in liquid-solid systems are given.•The models are compared with data from METCOR, METCOR-P, MASCA projects.•A model…”
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  8. 8

    Influence of corium oxidation on fission product release from molten pool by Bechta, S.V., Krushinov, E.V., Vitol, S.A., Khabensky, V.B., Kotova, S.Yu, Sulatsky, A.A., Gusarov, V.V., Almyashev, V.I., Ducros, G., Journeau, C., Bottomley, D., Clément, B., Herranz, L., Guentay, S., Trambauer, K., Auvinen, A., Bezlepkin, V.V.

    Published in Nuclear engineering and design (01-05-2010)
    “…Qualitative and quantitative determination of the release of low-volatile fission products and core materials from molten oxidic corium was investigated in the…”
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  9. 9

    VVER vessel steel corrosion at interaction with molten corium in oxidizing atmosphere by Bechta, S.V., Granovsky, V.S., Khabensky, V.B., Krushinov, E.V., Vitol, S.A., Sulatsky, A.A., Gusarov, V.V., Almiashev, V.I., Lopukh, D.B., Bottomley, D., Fischer, M., Piluso, P., Miassoedov, A., Tromm, W., Altstadt, E., Fichot, F., Kymalainen, O.

    Published in Nuclear engineering and design (01-06-2009)
    “…The long-term in-vessel corium retention (IVR) in the lower head bears a risk of the vessel wall deterioration caused by steel corrosion. The ISTC METCOR…”
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    Water boiling on the corium melt surface under VVER severe accident conditions by Bechta, S.V, Vitol, S.A, Krushinov, E.V, Granovsky, V.S, Sulatsky, A.A, Khabensky, V.B, Lopukh, D.B, Petrov, Yu.B, Pechenkov, A.Yu

    Published in Nuclear engineering and design (2000)
    “…Experimental results are presented on the interaction of corium melt with water supplied on its surface. The tests were conducted in the ‘Rasplav-2’…”
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  12. 12

    Oxidation effects during corium melt in-vessel retention by Almyashev, V.I., Granovsky, V.S., Khabensky, V.B., Krushinov, E.V., Sulatsky, A.A., Vitol, S.A., Gusarov, V.V., Bechta, S., Barrachin, M., Fichot, F., Bottomley, P.D., Fischer, M., Piluso, P.

    Published in Nuclear engineering and design (15-08-2016)
    “…•Corium–steel interaction tests were re-examined particularly for transient processes.•Oxidation of corium melt was sensitive to oxidant supply and surface…”
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