Výsledky vyhledávání - "E.V. Krushinov"

Modeling of Molten Corium Oxidation in the Presence of an Oxide Crust on the Melt Surface

Autor: V.I. Almjashev, E.V. Krushinov, V. V. Gusarov, V.B. Khabensky, V. S. Granovsky, S.Yu. Kotova, S. A. Vitol

Publikováno v: Technical Physics. 66:221-228

In the case of a severe accident at a nuclear power plant with light-water reactors, the most effective method for localization of the formed melt (corium) is its retention in the cooled reactor vessel whose integrity depends on the heat flux from th

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::97beddadfe69b383c92205965da832a7
https://doi.org/10.1134/s1063784221020146

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Experimental study of transient phenomena in the three-liquid oxidic-metallic corium pool

Autor: S.Yu. Kotova, Manfred Fischer, Florian Fichot, V.I. Almjashev, C. Le Guennic, R. Le Tellier, E.V. Krushinov, S. A. Vitol, N. Bakouta, V. V. Gusarov, A.A. Sulatsky, B. Michel, V. S. Granovsky, V.B. Khabensky, Pascal Piluso

Publikováno v: Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2018, 332, pp.31-37. ⟨10.1016/j.nucengdes.2018.03.004⟩

International audience; Non-steady physicochemical phenomena in the three-liquid molten pool of prototypic corium are studied in the context of in-vessel melt retention problem. Experiments are made on the Rasplav-3 test facility within the CORDEB pr

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6b0d245bb9c13166df58f551bc0defae
https://hal.archives-ouvertes.fr/hal-02874505

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Effect of temperature gradient on chemical element partitioning in corium pool during in-vessel retention

Autor: E.V. Krushinov, D. Bottomley, A. Miassoedov, V. V. Gusarov, V.B. Khabensky, Pascal Piluso, S. A. Vitol, V. S. Granovsky, V.I. Almjashev, Sevostian Bechta, S. Hellmann, Marc Barrachin, S. J. Kotova, W. Tromm, A.A. Sulatsky, Manfred Fischer

Publikováno v: Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2018, 327, pp.82-91. ⟨10.1016/j.nucengdes.2017.11.030⟩

International audience; The paper presents some results of the ISTC (International Science and Technology Center)-financed project ‘Investigation of Corium Melt Interaction with NPP Reactor Vessel Steel’ (METCOR). In the METCOR experiments the me

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b10fc23e816bcb00add952bc5d0a9c4a
https://hal.archives-ouvertes.fr/hal-02871823

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Oxidation kinetics of corium pool

Autor: V.B. Khabensky, S. Hellmann, Pascal Piluso, S.Yu. Kotova, W. Tromm, Manfred Fischer, E.V. Krushinov, S. A. Vitol, Marc Barrachin, S.A. Smirnov, D. Bottomley, A. Miassoedov, V. S. Granovsky, A.A. Sulatsky

Publikováno v: Nuclear Engineering and Design. 262:168-179

Experimental, theoretical and numerical studies of oxidation kinetics of an open surface corium pool have been reported. The experiments have been carried out within OECD MASCA program and ISTC METCOR, METCOR-P and EVAN projects. It has been shown th

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::51b0e1817644b5c9e41d2429b0cad55b
https://doi.org/10.1016/j.nucengdes.2013.04.025

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Formation of a nuclear reactor’s molten core bath in a crucible-type corium catcher for a nuclear power station equipped with VVER reactors

Autor: M. B. Sulatskaya, S. V. Beshta, V. V. Gusarov, V. B. Khabenskii, V. I. Al’myashev, A. A. Sulatskii, S. V. Kovtunova, V. S. Granovskii, E. K. Kalyago, S. A. Vitol, E.V. Krushinov

Publikováno v: Thermal Engineering. 58:424-428

Results from a calculation study on analyzing the formation of a melt bath in a crucible-type catcher for the conditions of a severe accident at a nuclear power station equipped with VVER-1000 reactors are presented. It is shown that the heat loads e

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::03ea81a463cb8ce0cf3673f56e753f90
https://doi.org/10.1134/s0040601511050041

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Operation of thermal protection shields used in the corium catcher at a nuclear power station equipped with VVER reactors

Autor: S. V. Beshta, E.V. Krushinov, V.B. Khabensky, S. A. Vitol, V. S. Granovsky, A. A. Sulatskii

Publikováno v: Thermal Engineering. 58:310-316

We present the results from experiments confirming the effectiveness of thermal shields used in the design of the ex-vessel corium catcher at nuclear power stations equipped with VVER reactors for limiting the radiation heat loads on the overlying st

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::7c46306b661b8fb6182564869d3bf3e9
https://doi.org/10.1134/s0040601511040069

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The interaction of nuclear reactor core melt with oxide sacrificial material of localization device for a nuclear power plant with water-moderated water-cooled power reactor

Autor: V. F. Strizhov, V. V. Gusarov, S. A. Vitol, V. B. Khabenskii, E.V. Krushinov, S. V. Beshta, V. S. Granovskii, V. G. Asmolov, A. A. Sulatskii, V. I. Al’myashev

Publikováno v: High Temperature. 45:22-31

The basic results are given of an experimental investigation of the interaction oxide corium melt containing unoxidized zirconium with the sacrificial material of the device for localization of the core melt of a water-moderated water-cooled power re

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5017677d80deae83b0954e0b7938aa9e
https://doi.org/10.1134/s0018151x0701004x

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