Experimental studies of oxidic molten corium–vessel steel interaction

Bechta, Sevostian; Khabensky, V.B.; Vitol, S. A.; Krushinov, E.V.; Lopukh, D.B.; Petrov, Yu. B.; Petchenkov, A.Yu.; Kulagin, I. V.; Granovsky, V.S.; Kovtunova, S. V.; Martinov, V.V.; Гусаров, В. В.

doi:10.1016/s0029-5493(01)00377-6

Cited by 17 publications

(5 citation statements)

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“…Temperature is thus a determining factor to the resistance of the ZrC coating to the UO 2 -Al 2 O 3 mixture. It can be also concluded that ZrC can be used as protective coating for graphite crucibles in case of oxide melt UO 2 [26]. The load was prepared in a mortar and heated in a ZrC-coated crucible up to 2100°C (±100°C).…”

Section: 222mentioning

confidence: 99%

“…This method of direct inductive heating of electrically conductive melts is for example used in COMETA facility (NRI, Czech Republic) [1] for the investigation of phase diagrams of systems containing UO 2 and other refractory oxides. It is also used in corium-steel interaction melt tests in RASPLAV-2 facility (NITI, Russia) [2]. Another solution is the use of hot crucibles, for which a very refractory and chemically stable material is needed.…”

Section: Introductionmentioning

confidence: 99%

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Zirconium carbide coating for corium experiments related to water-cooled and sodium-cooled reactors

Plevacova

Journeau

Piluso

et al. 2011

Journal of Nuclear Materials

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Section: 222mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Zirconium carbide coating for corium experiments related to water-cooled and sodium-cooled reactors

Plevacova

Journeau

Piluso

et al. 2011

Journal of Nuclear Materials

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“…Indeed, apart from the functional and economic advantages, this is a sole material whose interaction with the core melt has been studied to date when solving the problem associated with the retention of the melt in the reactor vessel [16,17]. The use of a steel as a component of the sacrificial material ensures the solution of the following basic problems:…”

Section: Analysis and The Choicementioning

confidence: 99%

Physicochemical modeling and analysis of the interaction between a core melt of the nuclear reactor and a sacrificial material

et al. 2005

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The problems regarding the design of a new class of materials, namely, sacrificial materials for use in devices intended for localization of a core melt of the nuclear reactor, are considered. Criteria are proposed for the proper choice of the chemical composition of a sacrificial material, as well as of the composition and microstructure of its constituents. The possible alternatives are outlined and analyzed. The results of designing a variant of the composition of sacrificial materials are presented. The experimental data on the interaction of an oxide sacrificial material with simulators of the metal and oxide phases of the core melt are discussed. A new type of combustion of materials, namely, the liquid-phase combustion, is revealed. It is demonstrated that the material designed can be used in systems intended for localization of a core melt of the nuclear reactor.

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“…Introduction. The cold crucible technology has been selected in this project because it has already proven his ability to melt corium thanks to Korean [1,2] and Russian [3,4] works but only for lower mass. Simulation of such induction furnace is quite well known in the CEA Marcoule for vitrifiction purposes [5,6].…”

mentioning

confidence: 99%