Research on the energy characteristics of reactor coolant pump under flow coastdown transient

Ye, Daoxing; Anlin, Liu; Luo, Yimin; Chen, Jun-Lin; Bo, Yu; Lai, Xide; Gou, Qiuqin

doi:10.1016/j.anucene.2022.109081

Cited by 4 publications

(2 citation statements)

References 7 publications

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“…Literature [12] studied the influence of force deformation and thermal deformation on the performance of hydrostatic mechanical seals by establishing a two-dimensional thermoelastic hydrodynamic lubrication model (TEHD). Literature [13] simplifies the seal ring into an axisymmetric model and analyzes the force deformation of the seal ring by using the ring theory and two-dimensional finite element model, respectively. The results show that this method has a good effect on calculating the deformation of complex seal rings.…”

Section: Related Workmentioning

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: Related Workmentioning

confidence: 99%

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

2022

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“…Specifically, a single fluctuation is referred to as a pressure pulsation [6]. Pressure pulsation is an important factor causing unstable phenomena such as vibration and noise in reactor coolant pumps, and severe pulsation can lead to the occurrence of nuclear accidents [7]. Xu Zhang et al [8] employed Fluent to numerically calculate the unsteady threedimensional flow of the RCP and found that the amplitude of pressure pulsation reached its maximum value between the impeller and the diffuser, and the dissipation rate of pressure pulsation waves in the impeller channel was greater than that in the diffuser channel.…”

Section: Introductionmentioning

confidence: 99%

Study on unsteady characteristics of the reactor coolant pump under non-uniform inflow

Zhang,

Zhang

et al. 2024

J. Phys.: Conf. Ser.

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The primary circuit of a nuclear power plant contains a steam generator (SG) and two vertical reactor coolant pumps (RCPs). Two RCPs are installed at the bottom of the SG. The structure of the channel-head of the SG is special, which leads to uneven flow from the RCP inlet and affects the operation performance of the pump. Taking the RCP of the third-generation reactor as the research object, the unsteady characteristics of the third-generation RCP under non-uniform inflow conditions were investigated using CFD, and the pressure pulsation characteristics inside the RCP were mainly studied. A series of monitoring points were set at the channel of the channel-head, impeller, diffuser and casing section respectively to study the influence of non-uniform flow on the pressure fluctuation and radial force distribution of the RCP. The results show that non-uniform inflow can cause instability in pressure fluctuations in the “throat” region of the channel-head. The interaction between the impeller and diffuser can cause pressure pulsation from the impeller outlet to the diffuser inlet, potentially impacting the safe and stable operation of the RCP. This research provides certain theoretical support for the design of RCPs under the condition of non-uniform inflow.

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Research on energy loss characteristics during transient process of reactor coolant pump shaft stuck accident

Guo

et al. 2023

Annals of Nuclear Energy

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Research on the energy characteristics of reactor coolant pump under flow coastdown transient

Cited by 4 publications

References 7 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

Study on unsteady characteristics of the reactor coolant pump under non-uniform inflow

Research on energy loss characteristics during transient process of reactor coolant pump shaft stuck accident

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