The paper deals with the present-day tendencies for development of a next-generation thermal-hydraulic code intended for analysis of emergency processes in the cooling systems of nuclear reactors. It is found necessary to provide a multidimensional description of thermal-hydraulic processes for a number of emergency conditions. Analysis is made of the possibilities of applying high-accuracy numerical methods developed for simulating two-phase processes. The main problems involved in mathematical simulation of two-phase flows are defined.
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