Analysis of the integrity of the reactor vessel under accident conditions with partial or complete destruction of the core is a key aspect of validating the safety of a reactor facility with VVER. When cooling is lost for a prolonged period of time, movement and accumulation of fused fragments of the core at the bottom of the vessel formation of a melt pool are possible. The interaction of high-temperature melt with vessel steel during such accidents is a quite complicated process, accompanied by heating and melting of the vessel.A comprehensive study of the thermal and strength aspects of the behavior of reactor vessels during a serious accident was the subject of attention in many foreign research programs. An examination of individual aspects of thermal and deformation behavior of VVER vessels during similar accidents [1][2][3][4][5] has shown that the time and character of vessel deformation prior to failure are largely determined by the thermal conditions on the outer surface and by the minimum residual thickness in the zone of melting of its wall. The excess vessel pressure and the size of the melt zone have a decisive effect on the time to failure and on the deformation of the vessel during a serious accident.The study of the thermal mechanical behavior of a VVER vessel during accidents with destruction of the core is based on thermal and strength analysis. The size of the melt zone (the residual thickness of the wall, extent, its location) and the temperature state of the vessel wall in this zone are determined by the concrete conditions of the flow of the accident. Consequently, there is justification for assuming a priori that the melting zone lies on the cylindrical shell of the VVER-440 vessel in the zone where it joins with the elliptical bottom (Fig. 1). This scheme corresponds in the case of complete or partial destruction of the core and the formation in the course of the accident of a stratified melt pool, when a layer of fused steel, resulting in the most intense melting of the vessel region where they come into contact with one another, is present above its oxide part.The thermomechanical computer codes [6-8] make it possible to simulate numerically the thermal and the thermomechanical state of a reactor vessel under conditions of heating, melting, and creep. The numerical simulation in our work made it possible to obtain parametric relations describing the time to failure and the magnitude of the vertical displacement of the bottom of the VVER vessel, at the bottom of which a stratified melt pool has formed, without performing long and difficult thermal and strength calculations.Method and Object of Investigation. The object of this investigation was a fragment of a VVER-440 vessel, consisting of the bottom and lower part of the cylindrical shell of the vessel. The thickness of the wall and the internal radius of the shell were 150 and 1780 mm, respectively. The physicomechanical characteristics of the vessels steel 15Kh2NMFA-A in the temperature range 300-1573 K were used in the numerical sim...