Abstract
Shock phenomena in a two-phase flow caused by a quick valve closure in the cooling system of a nuclear reactor have attracted special interest for the safety assessment of LOCA. In this report, analyses of the shock phenomena in a two-component two-phase bubbly flow by a two-velocity model, a homogeneous model, and a pressure wave reflection model are presented. Based on the comparisons of these analytical results with experimental results, the modelling and calculation techniques for various cases of void fraction distribution along the tube are discussed.
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