Experimental study on transient characteristics of reactor coolant pump under rotor seizure accident

Wang, Xiuli; Lu, Yonghao; Zhu, Rong; Fu, Qiang; Chen, Yi-Ming; Zhong, Weiyuan

doi:10.1016/j.anucene.2019.107039

Cited by 16 publications

(10 citation statements)

References 8 publications

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“…Reactor coolant pump (RCP) is the "heart" of nuclear power plant, and its main function is to pump the coolant required by the reactor into the reactor system, so that the coolant can be recycled in the reactor system [4,5]. According to the different sealing forms of the RCP, the RCP is divided into shaft seal pump and shielded pump.…”

Section: Introductionmentioning

confidence: 99%

Friction Performance Analysis of Reactor Coolant Pump Shaft Seal Based on Sensor and Computer Simulation

2022

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In recent years, the state has put forward a grand plan to develop nuclear power in order to control environmental pollution and carbon emissions. In nuclear power plants, mechanical seals for reactor coolant pump play an important role in nuclear power safety production. However, China cannot independently produce such mechanical seals, and they are blocked by foreign related technologies, which has seriously affected China’s nuclear power development plan and the overall safety of China’s nuclear power operation. Under this background, this paper studies the friction performance of the shaft seal of the reactor coolant pump, uses the sensor to obtain the data of friction factors such as low-pressure leakage, effectively monitors the low-pressure leakage through calculation and simulation modeling, truly reflects the operating state of the reactor coolant pump, and provides a new research direction and experimental basis for further analysis of the friction performance of the shaft seal of the reactor coolant pump. The results show that under the joint action of the pressure difference and the force generated by the deformation of the moving ring plate, the cone angle formed on the seal end face is 1300.9 μ convergence gap of rad. When the inlet water temperature is 65°C, the leakage rate is 1867.8 L/h. The deformation of the moving ring deformation ring plate can hinder the increase of the deformation cone angle of the moving ring. The greater the thickness of the moving ring deformation ring plate, the greater the seal leakage rate. The inlet temperature of the sealing medium and the friction performance of the material also have an impact on the sealing performance.

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Section: Introductionmentioning

confidence: 99%

Friction Performance Analysis of Reactor Coolant Pump Shaft Seal Based on Sensor and Computer Simulation

2022

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“…Compared with the computational fluid dynamic methods, experimental measurements are the most direct ways to study pressure pulsation characteristics 14–16 . Pei et al experimentally investigated the nonlinear pressure pulsation characteristics in a Residual Heat Removal Pump 17 .…”

Section: Introductionmentioning

confidence: 99%

“…13 Compared with the computational fluid dynamic methods, experimental measurements are the most direct ways to study pressure pulsation characteristics. [14][15][16] Pei et al experimentally investigated the nonlinear pressure pulsation characteristics in a Residual Heat Removal Pump. 17 Xu et al researched the unsteady pressure pulsation characteristics in an RCP with a steamgenerator simulator, and the influence of rotational speed on pressure pulsation was investigated.…”

Section: Introductionmentioning

confidence: 99%

Experimental investigation on the unsteady pressure pulsation and vibration of a nuclear pump test loop

Zhou

Dong

et al. 2022

Energy Science & Engineering

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The nuclear reactor coolant pump (RCP) is the key equipment of the Pressurized Water Reactor, of which the coolant circulation inherently brings flow fluctuation and, therefore, flow-induced vibration exists, which is detrimental to the safe and stable operation of nuclear power plants.Experiments were carried out on a nuclear pump test loop to investigate the characteristics of pressure pulsation and vibration under various rotational speeds and operational temperatures. Signals of pressure pulsation and vibration synchronously measured from the sensors located among the test loop and the bottom of the motor were analyzed by the Root Mean Square and the Fast Fourier Transform methods. Pronounced pressure pulsation peaks corresponding to the blade passage frequency and its higher harmonics are captured, and pressure pulsation amplitude variations are closely associated with the sensor positions and operating conditions. Vibration magnitude along the outlet direction of the nuclear RCP is the largest and increases with the increasing rotational speed but not the operating temperature. Finally, a coherent analysis was conducted between the vibration at the bottom of the motor and the unsteady pressure pulsation in the test loop. This study can provide meaningful scientific guidance in practical engineering applications.

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“…Kim et al (2014) analyzed the transient characteristics of pump-rising pipeline system with an air chamber using the method of characteristics. Wang et al, (2020) studied the transient characteristic of RCP under the condition of the rotor seizure accident by experiment. Fu et al (2020) conducted experimental and numerical studies of the transient characteristics during the start-up process of the axial flow pump.…”

Section: Introductionmentioning

confidence: 99%

Study on Hydraulic Characteristics of Reactor Coolant Pump Shutdown Transition Process Based on Primary Circuit Closed System

Zhang

et al. 2022

Front. Energy Res.

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According to the structural characteristics of a steam generator and a reactor pressure vessel, the reactor primary circuit system of HPR1000 is simplified to make the reactor coolant pump (RCP) characteristics match the resistance characteristics of the system pipeline, so a simplified model of reactor primary circuit closed system is formed. On this basis, the RCP shutdown accident in a single circuit of the reactor is numerically simulated. Results show that the pressure in the pipeline system has changed greatly compared. The flow rate drops rapidly and decreases to 1.7% of stable operation at 10s. The torque drops sharply to −51.89% of stable operation, and then rises slowly to zero. The pressure at the inlet and outlet of the impeller changes dramatically which leads to the change of blade load and the velocity in the impeller passage decreases gradually. The pressure and velocity in the guide vane continue to decrease.

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Experimental study on transient characteristics of reactor coolant pump under rotor seizure accident

Cited by 16 publications

References 8 publications

Friction Performance Analysis of Reactor Coolant Pump Shaft Seal Based on Sensor and Computer Simulation

Friction Performance Analysis of Reactor Coolant Pump Shaft Seal Based on Sensor and Computer Simulation

Experimental investigation on the unsteady pressure pulsation and vibration of a nuclear pump test loop

Study on Hydraulic Characteristics of Reactor Coolant Pump Shutdown Transition Process Based on Primary Circuit Closed System

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