Numerical study on the effect of the diffuser blade trailing edge profile on flow instability in a nuclear reactor coolant pump

2017 ◽  
Vol 322 ◽  
pp. 92-103 ◽  
Author(s):  
Dan Ni ◽  
Minguan Yang ◽  
Bo Gao ◽  
Ning Zhang ◽  
Zhong Li
Keyword(s):  
Nuclear Reactor ◽  
Flow Instability ◽  
Numerical Study ◽  
Trailing Edge ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Edge Profile

Unsteady Flow Structures and Pressure Pulsations in a Nuclear Reactor Coolant Pump With Spherical Casing

2017 ◽  
Vol 139 (5) ◽  
Author(s):  
Dan Ni ◽  
Minguan Yang ◽  
Ning Zhang ◽  
Bo Gao ◽  
Zhong Li
Keyword(s):  
Unsteady Flow ◽  
Nuclear Reactor ◽  
Internal Flow ◽  
Wake Flow ◽  
Flow Structures ◽  
Pressure Pulsations ◽  
Trailing Edge ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Vorticity Distribution

Severe vibrations induced by flow instabilities in the nuclear reactor coolant pump (RCP) are detrimental to the safe operation of the pump. Due to the particular spherical casing in the RCP, the internal flow structures are extremely ambiguity and complicated. The goal of the present work is to shed comprehensive light on the unsteady flow structures and its correlation with the pressure pulsations by using large eddy simulation (LES) method of the RCP. The vorticity distribution and the shedding vortex from the blade trailing edge are depicted in detail. Furthermore, the internal correlations between the flow unsteadiness and pressure pulsation are illustrated in some special regions of the RCP. Evidently, some main excitation components in the pressure spectra are excited by the shedding vortex. Besides, components at blade passing frequency (fBPF) are closely associated with rotor–stator interaction between the wake flow from the impeller outlet and unsteadiness vortexes shedding from the diffuser blade trailing edge. It is thought to be that the pressure pulsations of the RCP are closely associated with the corresponding vorticity distribution and the unsteady vortex shedding effect.

Dynamic measurements on unsteady pressure pulsations and flow distributions in a nuclear reactor coolant pump

Energy ◽  
2020 ◽  
Vol 198 ◽  
pp. 117305 ◽  
Author(s):  
Dan Ni ◽  
Ning Zhang ◽  
Bo Gao ◽  
Zhong Li ◽  
Minguan Yang
Keyword(s):  
Nuclear Reactor ◽  
Pressure Pulsations ◽  
Dynamic Measurements ◽  
Coolant Pump ◽  
Unsteady Pressure ◽  
Reactor Coolant

scholarly journals Flow Unsteadiness and Pressure Pulsations in a Nuclear Reactor Coolant Pump

2016 ◽  
Vol 62 (4) ◽  
pp. 231-242 ◽  
Author(s):  
Dan Ni ◽  
Minguan Yang ◽  
Bo Gao ◽  
Ning Zhang ◽  
Zhong Li
Keyword(s):  
Nuclear Reactor ◽  
Pressure Pulsations ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Flow Unsteadiness

Influence of Guide Vane Wrap Angle Key Design Parameters on Hydraulic Performance of Nuclear Reactor Coolant Pump

2014 ◽  
Vol 721 ◽  
pp. 73-77 ◽  
Author(s):  
Wei Nan Jin ◽  
Rong Xie ◽  
Mu Ting Hao ◽  
Xiao Fang Wang
Keyword(s):  
Flow Field ◽  
Nuclear Reactor ◽  
Guide Vane ◽  
Three Dimensional ◽  
Internal Flow ◽  
Hydraulic Performance ◽  
Design Parameters ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Wrap Angle

To study the effects of guide vane with different vane wrap angles and relative positions of outlet edge on hydraulic performance of nuclear reactor coolant pump, three-dimensional steady numerical simulations were performed by using CFD commercial software Numeca. The results show that the vane wrap angle changes the head and power characteristics by changing the relative velocity angle in vane outlet. The inner flow field changes while the wrap angle changes. With the wrap angle increases, the shock loss in volute is reducing, but the friction loss in vane passages is getting large. So there exists an optimum wrap angle and relative positions of outlet edge that corresponds to the highest efficiency of a pump. Numerical simulation is performed with the two key design parameters optimized through surrogate model, the internal flow field is improved and then the hydraulic efficiency is improved.

scholarly journals Influence of Circumferential Placement Position of Guide Vanes on Performance and Dynamic Characteristics of Nuclear Reactor Coolant Pump

2020 ◽  
Vol 2020 ◽  
pp. 1-12
Author(s):  
Xiaorui Cheng ◽  
Boru Lv ◽  
Chenying Ji ◽  
Ningning Jia ◽  
Dorah N
Keyword(s):  
Nuclear Reactor ◽  
Guide Vane ◽  
Equivalent Stress ◽  
Hydraulic Loss ◽  
Stress Strain ◽  
Coolant Pump ◽  
Guide Vanes ◽  
Reactor Coolant ◽  
Maximum Equivalent Stress ◽  
Exit Edge

In order to study the influence of the circumferential placement position of the guide vane on the flow field and stress-strain of a nuclear reactor coolant pump, the CAP1400 nuclear reactor coolant pump is taken as the research object. Based on numerical calculation and test results, the influence of circumferential placement position of the guide vane on the performance of the nuclear reactor coolant pump and stress-strain of guide vanes are analyzed by the unidirectional fluid-solid coupling method. The results show that the physical model and calculation method used in the study can accurately reflect the influence of the circumferential placement position of the guide vane on the nuclear reactor coolant pump. In the design condition, guide vane position has a great influence on the nuclear reactor coolant pump efficiency value, suction surface of the guide vane blade, and the maximum equivalent stress on the hub. However, it has a weak effect on the head value, pressure surface of the guide vane blade, and the maximum equivalent stress on the shroud. When the center line of the outlet diffuser channel of the case is located at the center of the outlet of flow channel of the guide vane, it is an optimal guide vane circumferential placement position, which can reduce the hydraulic loss of half of the case. Finally, it is found that the high stress concentration area is at the intersection of the exit edge of the vane blade and the front and rear cover, and the exit edge of the guide vane blade and its intersection with the front cover are areas where the strength damage is most likely to occur. This study provides a reference for nuclear reactor coolant pump installation, shock absorption design, and structural optimization.

scholarly journals Stress Analysis for Reactor Coolant Pump Nozzle of Nuclear Reactor Pressure Vessel

2013 ◽  
Vol 01 (06) ◽  
pp. 62-64
Author(s):  
Lijing Wen ◽  
Chao Guo ◽  
Tieping Li ◽  
Chunming Zhang
Keyword(s):  
Stress Analysis ◽  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Reactor Pressure Vessel ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Reactor Pressure
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