Abstract
In order to study the internal transient pressure surge law of the reactor coolant pump (RCP) during the shaft stuck transition. Based on HPR1000 reactor primary circuit closed system (RPCCS), the steam generator tube bundle area and the reactor pressure vessel core area are simplified. The hydraulic characteristics of the RCP can be matched with the resistance characteristics of the system pipeline. The transient numerical calculation of the RCP shaft stuck transition process is carried out by establishing a three-dimensional simplified model of RPCCS. The pressure surge characteristics of each monitoring point in the impeller, guide vane and volute passage under different shaft stuck mass flow periods (TQi) are obtained. The collected transient pressure surge data is analyzed by wavelet transform method (WTM). The results show that: in the stable operation state, the wavelet intensity value in the high frequency band in each flow passage change periodically and alternately. During the process of shaft stuck transition, the demarcation point (TN0) is taken when the impeller speed just drops to 0 r/min. The pressure of each monitoring point in the flow passage reaches the extreme value at this point, and then gradually tends to the reference pressure of 15.5 MPa. The regularity of high-band wavelet response in each flow passage of the RCP is gradually destroyed. Taking TN0 as the demarcation point, the low-band wavelet response firstly increases and then decreases. And the low-band wavelet response in the guide vane passage is generally higher than that in other flow passages at the same time. In this process, there is significantly different in the vortex structures on both sides of the impeller blade. The high vorticity magnitude regions appear in the impeller passage on the side of the blade working surface and in the guide vane passage. In this paper, by revealing the time–frequency characteristics of pressure surge in the RCP under shaft stuck accident (SSA), which provides a certain support for the dynamic safety evaluation of the reactor hydrodynamic system.
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