2006•Thermal EngineeringRequires access

A combined thermal and strength analysis of the behavior of a VVER-440 reactor’s vessel during an accident involving core melting

N.G. Rassokhin, V. D. Loktionov, E. S. Mukhtarov

Abstract

Results from parametric calculations of the thermal and strength behavior of a VVER-440 reactor’s vessel during a beyond-design-basis accident are presented. The ranges of gage pressure inside the vessel and the conditions of externally cooling the reactor with water are presented under which the corium that appears in the reactor vessel during a severe accident can be held there for a long time.

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Key concepts: VVER, Reactor pressure vessel, Corium, Nuclear engineering, Pressure vessel, Nuclear reactor core, Pressurized water reactor, Core (optical fiber)