Abstract
Vibration and dynamic stress caused by the interaction between the fluid and the structure can affect the reliability of pumps. This study presents an investigation of internal flow field and the structure response of residual heat removal pump using a combined calculation for turbulent flow, and the structure response of rotor was first defined using a two-way coupling method. For the calculation, the flow field is based on the shear stress transport k–ω turbulence model and the structure response is determined using an elastic structural dynamic equation. The results show that the domain frequencies of pressure fluctuations of monitors on the outlet of impeller are the integer multiples of rotating shaft frequency ( fn) and the amplitude of the relatively large pressure fluctuation peak is the lowest under the design flow rate operating condition. Meanwhile, the time-average radial force value at the design flow rate condition is the smallest and the hydraulic force magnitude at the maximum operating flow rate condition is the largest, and phase difference can be clearly seen among the results obtained under different flow rates. Furthermore, the relatively large stress of rotor for all operating conditions is the biggest at shaft shoulder where the bearing is installed, and it increases with flow rate.
Highlights
Residual heat removal pumps (RHRPs) are key equipment of residual heat removal (RRA) system in 1000MW nuclear power plants, and their level of safety requirements is second only to nuclear reactor coolant pumps
The RHRPs are used for the following purpose: first, circulating primary coolant through RRA heat exchangers to remove residual heat, thereby achieving and/or maintaining cold shutdown of unit; second, draining the coolant in the reactor cavity
In order to ensure the safety of nuclear power plants, the RHRPs should have low vibrations under different operating conditions
Summary
Residual heat removal pumps (RHRPs) are key equipment of residual heat removal (RRA) system in 1000MW nuclear power plants, and their level of safety requirements is second only to nuclear reactor coolant pumps. Pei et al.[14] studied the impeller oscillations induced by periodically unsteady flow in a single-blade pump considering FSI simulations with strong two-way coupling and compared the numerical and experimental results under off-design conditions.
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