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621.177Integrated investigations of the hydraulic characteristics of water-leveling pipes of 2.3 m in diameter separator drums (bench stand investigations, industrial tests, and computational analysis) were performed for the second power-generating unit of the Kursk nuclear power plant.In accordance with the results of [i], a determining factor in formulating an optimal procedure of investigation is the development of a mathematical model that describes the connections in the hydraulic system, including two neighboring separator drums, a part of the water-lowering channel of the repeated force circulation loop (RFSL) with the intake collector, steam-discharge pipes (in this case, a high-pressure ring), water levelers, and steam bypass pipes. Figure 1 displays the computational scheme for the hydraulic system.The starting equations, formulated assuming that the pressure along the intake collector and in the high-pressure ring are constant, have the following form:P3 --APwl 4" /"/nc P dpt = P,c ;(i) P4 -AP~2 + (HBc + a)Pdo2 = P,e; PI --~ILPsl --(Hnc 4-a)p~' = Phpr; P2 -APs2 -HncP2 = Phpr; P3 -PI = H~t Pl + Hsl P'l';