V.B. Khabensky

Scientific Research Institute of Technology named after AP Aleksandrov

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ВВ

В. В. Гусаров

Ioffe Institute

Sevostian Bechta

KTH Royal Institute of Technology

V.S. Granovsky

Scientific Research Institute of Technology named after AP Aleksandrov

ЕК

Е.В. Крушинов

Scientific Research Institute of Technology named after AP Aleksandrov

V.I. Almjashev

Institute of Chemistry of Silicates named after I.V. Grebenshchikov

D. Bottomley

Joint Research Centre

S.A. Vitol

Scientific Research Institute of Technology named after AP Aleksandrov

A.A. Sulatsky

Scientific Research Institute of Technology named after AP Aleksandrov

W. Tromm

Karlsruhe Institute of Technology

D. B. Lopukh

Saint Petersburg State Electrotechnical University

Cooperative Institutions

Research Institute of Technology (Russia)

Russian Academy of Sciences

Scientific Research Institute of Technology named after AP Aleksandrov

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

CEA Cadarache

Direction des énergies

Saint Petersburg State Electrotechnical University

Institute of Chemistry of Silicates named after I.V. Grebenshchikov

Peter the Great St. Petersburg Polytechnic University

FZI Research Center for Information Technology

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Critical heat flux prediction in rod bundles under upward low mass flux densities

Nuclear Engineering and Design (1998)

V.B. Khabensky S. Malkin V.V. Shalia B.I. Nigmatulin

Mass flux

Critical mass (sociodynamics)

10.1016/s0029-5493(98)00156-3

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Citations (2)

Experimental study of oxidic-metallic melt oxidation

Nuclear Engineering and Design (2020)

A.A. Sulatsky V.I. Almjashev Vladimir S. Granovsky V.B. Khabensky Evgeniy V. Krushinov

Liquid metal

Corium

Molten metal

10.1016/j.nucengdes.2020.110618

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Citations (4)

New experimental results on the interaction of molten corium with reactor vessel steel

Sevostian Bechta V.B. Khabensky V.S. Granovsky Е.В. Крушинов S.A. Vitol

In order to justify the concept of in-vessel core melt retention, it is necessary to understand the thermal and physico-chemical phenomena. Especially the interaction of the molten pool with the reactor vessel during outside cooling needs to be understood. These phenomena are very complex, in particular, where interactions with the oxidic melt are concerned. In the early stages of the retention process, the oxidic corium and the vessel steel interact under the conditions of low oxygen potential in the melt. These conditions can be simulated by a molten corium having the composition UO{sub 2}/ZrO{sub 2}/Zr, where the degree of Zr-oxidation is in the range between 30 % (C-30) and 100 % (C-100). Corresponding experiments with prototypic melts at low oxygen potentials are being performed in the ISTC METCOR project 2. phase. These are: - MC 5 of corium composition 71w%UO{sub 2}-29w%ZrO{sub 2} (C-100) in neutral atmosphere (argon), - MC 6 of corium composition 76w%UO{sub 2}-9w%ZrO{sub 2}-15w%Zr (C{approx}30), also in argon. In test MC 5, the interaction of molten C-100 corium with a water-cooled steel specimen was studied for the following maximum temperatures at the specimen surface: 1075 deg. C, 1180 deg. C, 1315 deg. C and 1435 deg. C. Themore » total duration of the experiment was {approx} 36 hours. The MC 5 test serves as a reference test for determining the characteristics of the interaction between oxidic melt and steel specimen under the conditions of minimum chemical interaction potential. To investigate the effect of substoichiometry, test No 6 was then performed with sub-oxidized molten corium C{approx}30. The maximum surface temperature of the cooled steel specimen was held at {approx} 1400 deg. C. The test duration was {approx} 10 hours. The ablation phenomena were found to differ significantly from those observed both in the reference test, as well as in former tests with oxidized melts, as they involved the formation of a low-melting metallic phase at the interface which contains iron, zirconium and uranium. The paper summarizes the results of the experiments and of the performed posttest analysis for tests MC 5 and MC 6. (authors)« less

Corium

Source

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Citations (13)

Distribution of components between immiscible melts of a system under nonisothermal conditions

Glass Physics and Chemistry (2006)

В. В. Гусаров V.I. Almjashev V.B. Khabensky S. V. Beshta V.S. Granovsky

Redistribution

10.1134/s1087659606060083

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Citations (5)

ICONE11-36102 Core Catcher for Tianwan NPP with VVER-1000 reactor. Concept, Design and Justification

The Proceedings of the International Conference on Nuclear Engineering (ICONE) (2003)

S. V. Svetlov V. V. Bezlepkin I. V. Kukhtevich Sevostian Bechta V.S. Granovsky

VVER

Reactor design

10.1299/jsmeicone.2003.104

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Citations (2)

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

Nuclear Engineering and Design (2018)

V.I. Almjashev V.S. Granovsky V.B. Khabensky S.Yu. Kotova Е.В. Крушинов

Corium

Liquid metal

Molten metal

Transient (computer programming)

10.1016/j.nucengdes.2018.03.004

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Citations (25)

Oxidation effect on steel corrosion and thermal loads during corium melt in-vessel retention

Nuclear Engineering and Design (2014)

V.S. Granovsky V.B. Khabensky Е.В. Крушинов S.A. Vitol A.A. Sulatsky

During a severe accident with core meltdown, the in-vessel molten core retention is challenged by the vessel steel ablation due to thermal and physicochemical interaction of melt with steel. In accidents with oxidizing atmosphere above the melt surface, a low melting point UO2+x–ZrO2–FeOy corium pool can form. In this case ablation of the RPV steel interacting with the molten corium is a corrosion process. Experiments carried out within the International Scientific and Technology Center's (ISTC) METCOR Project have shown that the corrosion rate can vary and depends on both surface temperature of the RPV steel and oxygen potential of the melt. If the oxygen potential is low, the corrosion rate is controlled by the solid phase diffusion of Fe ions in the corrosion layer. At high oxygen potential and steel surface layer temperature of 1050 °C and higher, the corrosion rate intensifies because of corrosion layer liquefaction and liquid phase diffusion of Fe ions. The paper analyzes conditions under which corrosion intensification occurs and can impact on in-vessel melt retention (IVR).

Corium

High-Temperature Corrosion

Oxidizing agent

10.1016/j.nucengdes.2014.07.034

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Citations (8)

Oxidation kinetics of corium pool

Nuclear Engineering and Design (2013)

A.A. Sulatsky Sergey Smirnov V.S. Granovsky V.B. Khabensky Е.В. Крушинов

Corium

Oxidation process

10.1016/j.nucengdes.2013.04.025