Study on bidirectional fluid-solid coupling characteristics of reactor coolant pump under steady-state condition

Wang, Xiuli; Lu, Yonggang; Zhu, Rongsheng; Fu, Qiang; Yu, Haoqian; Chen, Yiming

doi:10.1016/j.net.2019.05.009

Cited by 23 publications

(4 citation statements)

References 4 publications

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“…Key et al [12] showed that the proper timing position between the rotor and the stator is conducive to improve the mechanical properties of the fluid and the internal flow. Wang et al [13] found that in the transient calculation, the average head of the nuclear reactor coolant pump decreased after coupling, which was closer to the test value. In off-design conditions, fluid instability will seriously affect the stability of the pumping station, so it is necessary to check the pumping station in advance.…”

Section: Introductionsupporting

confidence: 52%

Influence of the Impeller/Guide Vane Clearance Ratio on the Performances of a Nuclear Reactor Coolant Pump

Cheng¹,

Liu²,

B³

2022

Fluid Dynamics &Amp; Materials Processing

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Section: Introductionsupporting

confidence: 52%

Influence of the Impeller/Guide Vane Clearance Ratio on the Performances of a Nuclear Reactor Coolant Pump

Cheng¹,

Liu²,

B³

2022

Fluid Dynamics &Amp; Materials Processing

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“…The coupling deformation of the test pump during simulations is small, while the structure of the test pump is complex, and strong flow turbulence occurred within the pump after the start of the rotor seizure accident. Therefore, to obtain more accurate simulation results, the bidirectional fluid-solid coupling method [12] was utilized to solve the fluid field and rotor structure field inside the RCP, and the solution For the fluid domain, calculations were performed using the Reynolds-averaged Navier-Stokes (RANS) equations and the Shear Stress Transfer (SST) turbulence model [13,14]. The RANS equations consist of the continuity equation Eq.…”

Section: Fluid-solid Couplingmentioning

confidence: 99%

Transient Analysis of a Reactor Coolant Pump Rotor Seizure Nuclear Accident

An,

Zhong,

et al. 2024

FDMP

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The reactor coolant pump (RCP) rotor seizure accident is defined as a short-time seizure of the RCP rotor. This event typically leads to an abrupt flow decrease in the corresponding loop and an ensuing reactor and turbine trip. The significant reduction of core coolant flow while the reactor is being operated at full load can have very negative consequences. This potentially dangerous event is typically characterized by a complex transient behavior in terms of flow conditions and energy transformation, which need to be analyzed and understood. This study constructed transient flow and rotational speed mathematical models under various degrees of rotor seizure using the test data collected from a dedicated transient rotor seizure test system. Then, bidirectional fluid-solid coupling simulations were conducted to investigate the flow evolution mechanism. It is found that the influence of the impeller structure size and transient braking acceleration on the unsteady head (H u ) is dominant in rotor seizure accident events. Moreover, the present results also show that the rotational acceleration additional head (H u1 ) is much higher than the instantaneous head (H u2 ).

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“…Al-Obaidi [8] found that the number of impeller blades has a high impact on pressure, shear stress, magnitude velocity, axial velocity, radial velocity, tangential velocity, and average pressure, and he also [9] studied the behaviors of the flow field and pressure fluctuations in both time and frequency domains in an axial flow pump via the changing of various impeller blade angles. Li H [10] found that different impeller trailing edges can affect the efficiency of the pump; the thinner the trailing edge, the higher the efficiency. Wang H [11] variously tested slot structure geometric parameter combinations to explore this relationship: slot position p, slot width b 1 , slot deflection angle β, and slot depth h with (3-4) levels were selected for each factor on an L 16 orthogonal test table, and the results show that b 1 and h are the major factors influencing pump performance under small and rated flow conditions.…”

Section: Introductionmentioning

confidence: 99%

An Impeller Optimization Method for the High Specific Speed Mixed-Flow Reactor Coolant Pump Applied to Marine Nuclear Power

Zhao

et al. 2023

JMSE

Self Cite

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The reactor coolant pump (RCP) is the only rotating equipment in the primary circuit system of a nuclear power plant and the “heart” of the nuclear reactor. The L formula is defined, and the L/himp is introduced to study the influence of impeller blade type on the performance of the RCP. Twenty groups of models are designed, the concept of arc height ratio is proposed from the perspective of himp and L, and the distribution of internal entropy production within the impeller of the RCP under different Ls and himps of the impeller blade type is analyzed. The results show that when himp remains un-changed and L increases, the low-pressure area at the inlet of the impeller expands while the high-pressure area at the outlet decreases under the design flow or large flow conditions. The smoother blade profile reduces the occurrence of secondary flow phenomena and makes the RCP pressure distribution more uniform. Under design flow and large flow conditions, smaller L/himp and higher himp lead to higher efficiency and head performance. However, higher efficiency and lower head performance can be achieved under small flow conditions with larger L/himp and lower himp.

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Study on bidirectional fluid-solid coupling characteristics of reactor coolant pump under steady-state condition

Cited by 23 publications

References 4 publications

Influence of the Impeller/Guide Vane Clearance Ratio on the Performances of a Nuclear Reactor Coolant Pump

Influence of the Impeller/Guide Vane Clearance Ratio on the Performances of a Nuclear Reactor Coolant Pump

Transient Analysis of a Reactor Coolant Pump Rotor Seizure Nuclear Accident

An Impeller Optimization Method for the High Specific Speed Mixed-Flow Reactor Coolant Pump Applied to Marine Nuclear Power

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