The reactor coolant pump is an integral part of the reactor coolant pressure boundary. Its security rank is the highest level. The flow transient analysis is very necessary in the reactor coolant pump design and the nuclear reactor design. Based on the momentum conservation and momentum balance relations, The transient flow rate and the pump speed during a pump start-up are derived The analytical flow rate, the pump speed and the kinetic energy stored in the rotating parts are all non-dimensionalized. A comparison with Tsukamoto’s experimental results during the pump start-up shows good agreement. The curves of non-dimensional start-up flow rate, the pump speed and the kinetic energy stored in the rotating parts for different system parameter β are predicted and compared. The effect of β on the flow rate, the pump speed and the kinetic energy stored in the rotating parts is discussed according to the inertia of primary loop fluid and the pump moment of inertia. In addition, the prediction of the flow rate, the pump speed transient of Qinshan and Dayawan reactor coolant pumps and Takada’s test pump during start-up period are also performed.
- Fluids Engineering Division
Flow Transient in Primary Coolant System During Reactor Coolant Pump Start-Up Period
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Gao, H, Gao, F, Zhao, X, Chen, J, & Cao, X. "Flow Transient in Primary Coolant System During Reactor Coolant Pump Start-Up Period." Proceedings of the ASME 2013 Fluids Engineering Division Summer Meeting. Volume 1C, Symposia: Gas-Liquid Two-Phase Flows; Industrial and Environmental Applications of Fluid Mechanics; Issues and Perspectives in Automotive Flows; Liquid-Solids Flows; Multiscale Methods for Multiphase Flow; Noninvasive Measurements in Single and Multiphase Flows; Numerical Methods for Multiphase Flow; Transport Phenomena in Energy Conversion From Clean and Sustainable Resources; Transport Phenomena in Materials Processing and Manufacturing Processes; Transport Phenomena in Mixing; Turbulent Flows: Issues and Perspectives. Incline Village, Nevada, USA. July 7–11, 2013. V01CT26A008. ASME. https://doi.org/10.1115/FEDSM2013-16580
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