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- W2620021331 abstract "Pressure drops in a loop are consequence of the flow (except for gravity pressure drops). The consistent combination of mass flow rate and pressure drop determines the pumping power in all systems including water cooled nuclear reactors. The complexity of the issue may be grasped considering the following items: (a) two-phase flows; (b) singularities in the flow stream or at geometric discontinuities; (c) counter-current flow (liquid and steam); (d) flow reversal; (e) flashing of subcooled fluid including the extreme conditions of typical geysering. Pressure drops in a closed loop following loss of coolant accident (e.g., pressurized water reactor conditions, mainly) determine the fluid stagnation point location which may signify zero-flow and very low heat transfer coefficient. All of this constitutes a motivation for this chapter." @default.
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- W2620021331 date "2017-01-01" @default.
- W2620021331 modified "2023-09-27" @default.
- W2620021331 title "Pressure drops in nuclear thermal-hydraulics" @default.
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- W2620021331 doi "https://doi.org/10.1016/b978-0-08-100662-7.00008-7" @default.
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