Experimental Investigation on Power Consumption in Reactor Coolant Pumps with the Function of the Flywheel

2013 ◽  
Vol 744 ◽  
pp. 58-62
Author(s):  
Chun Ming Gong ◽  
Zheng Qiang Yao ◽  
Yao Zong Hou ◽  
Ya Bo Xue ◽  
De Cheng
Keyword(s):  
Experimental Investigation ◽  
Power Consumption ◽  
Experimental Method ◽  
Dynamic Characteristics ◽  
Nuclear Reactor ◽  
Simulation Analysis ◽  
Rotor System ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Special Working

This article mainly discusses the dynamic characteristics of the experimental rotor system under the abrupt power shut circumstances, and to search the distribution of the power consumption during special working processes with an experimental method. On the basis of the experimental results, the simulation analysis is carried out on the Andritz RCP, and therefore, the dynamic characteristics of the real nuclear reactor coolant pump can be forecast, which just meets the need of the safety running in nuclear plant.

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.

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