Abstract
A study was carried out of the hydrodynamics and heat transfer of two-phase flow in the main elements of the heat-exchange circuits of a nuclear power plant: axisymmetric annular channel and an assembly of vertical rods. The features of the distribution of the gas phase in the section of the working sections of the setup were studied. The dependences of the frictional stress and the heat transfer coefficient are obtained for various flow rates of liquid and gas. The interaction of one- and two-phase flows with barriers that overlap a portion of the cross-section of the channels by a spacer grid in the rod assembly and a partition covering 25% of the cross section of the annular channel is considered. The obtained data can be used for verification of modern computational codes.
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