Abstract
This paper presents results of the calculation analysis of processes of droplet entrainment of boric acid by steam flow at a loss of coolant accident (LOCA) on nuclear power plant (NPP) with WWER. A review of the available literature data on the research of this process is presented. It has been found that the existing data do not cover all the parameters, such as temperature, pressure and acid concentration, which are characteristic for a possible emergency situation at NPP with WWER. The dependence obtained by analysis allows estimating the size of droplet entrained by steam flow during an emergency process in WWER reactor plant with operation of a complex of passive safety systems.
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