V. G. Asmolov, A. A. Sulatskii, S. V. Beshta, V. S. Granovskii, V. B. Khabenskii, E. V. Krushinov, S. A. Vitol', V. I. Al'myashev, V. V. Gusarov, V. F. Strizhev, “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”, TVT, 2007, Volume 45, Issue 1,Pages <nobr>28

This article is cited in 13 papers

Thermophysical Properties of Materials

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

V. G. Asmolov^a, A. A. Sulatskii^b, S. V. Beshta^b, V. S. Granovskii^b, V. B. Khabenskii^b, E. V. Krushinov^b, S. A. Vitol'^b, V. I. Al'myashev^c, V. V. Gusarov^c, V. F. Strizhev^d

^a Russian Research Centre "Kurchatov Institute", Moscow
^b Alexandrov Research Institute of Technology
^c Institute of Silicate Chemistry of the Russian Academy of Sciences, St. Petersburg
^d Nuclear Safety Institute, RAS

Abstract: 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 reactor (VVER). The mechanism is determined and a model developed of interaction between suboxidized corium melt and sacrificial material.

UDC: 621.039

PACS: 44.35. + C

Received: 29.11.2005