Simulation of heat transfer processes in the containment shell of a nuclear power station with VVER reactors

Principles are formulated for accomplishing mathematical and physical simulation of aerohydrodynamical, thermal, and physicochemical processes in the containment shell of a nuclear power station in the event of a loss-of-coolant accident. Characteristics of a set of numerical codes KUPOL-FEI and of physical models 1, 2.5, 8, 100, and 3200 m 3 in volume are described. Preliminary results from partial verification of these codes, typical results from experiments, and a numerical analysis are presented