Experimental Study on PIV Measurement and CFD Investigation of the Internal Flow Characteristics in a Reactor Coolant Pump

被引:5
作者
Ni, Dan [1 ,2 ]
Lu, Hongzhong [1 ]
Huang, Shiyuan [2 ]
Lu, Sheng [1 ]
Zhang, Yang [3 ]
机构
[1] Shanghai Kaiquan Pump Grp Co Ltd, Shanghai 201800, Peoples R China
[2] Jiangsu Univ, Sch Energy & Power Engn, Zhenjiang 212013, Peoples R China
[3] Shanghai Marine Equipment Res Inst SMERI, Shanghai 200031, Peoples R China
基金
中国国家自然科学基金;
关键词
reactor coolant pump (RCP); internal flow characteristics; energy performance; PIV; velocity distribution; numerical calculation; TRAILING-EDGE PROFILE; PRESSURE PULSATIONS; DIFFUSER; FIELD; PERFORMANCE; VALIDATION; SIMULATION; MODELS;
D O I
10.3390/en16114345
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
The nuclear reactor coolant pump (RCP) is the core piece of equipment of a nuclear power plant (NPP). The energy performance and internal flow characteristics of RCPs are revealed by effective measurement methods, which are helpful to understand the flow mechanism of RCPs. The present work is intended to conduct an integrated study based on the energy performance test and Particle Image Velocimetry (PIV) flow-field non-contact measurement of the RCP. In addition, the prediction results of different turbulence models are compared with experimental results in detail. Through energy performance measurement and numerical calculation analysis, it can be found that various turbulence models have the ability to predict the performance of RCPs in engineering applications. At 0.8 similar to 1.2 phi(d) operating conditions, the maximum error is less than 10% and the minimum error is less than 0.1% by analyzing the energy performance of numerical calculations and experimental results. The PIV results show that the velocity of the discharge nozzle varies greatly from right (outlet of diffuser channel 2) to left (outlet of diffuser channel 12) due to different flow structures. Through the qualitative and quantitative comparison of the internal flow field, it can be concluded that, except for the low flow rate, compared with other computational models, the Realizable k-epsilon model can better predict the internal flow field of an RCP. The reasons for the experimental error and numerical calculation error are analyzed in detail, and the results can provide a reference for forecasting an RCP internal flow field with a special and complex structure.
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页数:21
相关论文
共 43 条
[1]   Potential uses of different sustainable concrete mixtures in gamma and neutrons shielding purposes [J].
Ali, Mohamed A. E. M. ;
Tawfic, A. F. ;
Abdelgawad, Mostafa A. ;
Wagih, Mohamed ;
Omar, A. .
PROGRESS IN NUCLEAR ENERGY, 2023, 157
[2]   Gamma and neutrons shielding using innovative fiber reinforced concrete [J].
Ali, Mohamed A. E. M. ;
Tawfic, A. F. ;
Abdelgawad, Mostafa A. ;
Mahdy, Mohamed ;
Omar, A. .
PROGRESS IN NUCLEAR ENERGY, 2022, 145
[3]  
[Anonymous], 2022, IPCC WGII sixth assessment report
[4]   Perspective Modeling nuclear energy's future role in decarbonized energy systems [J].
Bistline, John ;
Bragg-Sitton, Shannon ;
Cole, Wesley ;
Dixon, Brent ;
Eschmann, Erich ;
Ho, Jonathan ;
Kwon, Augustine ;
Martin, Laura ;
Murphy, Caitlin ;
Namovicz, Christopher ;
Sowder, Andrew .
ISCIENCE, 2023, 26 (02)
[5]   Investigations of energy distribution and loss characterization in a centrifugal impeller through PIV experiment [J].
Chen, Bo ;
Li, Xiaojun ;
Zhu, Zuchao .
OCEAN ENGINEERING, 2022, 247
[6]   Nuclear and New Energy Technology [J].
Davydov, Roman .
ENERGIES, 2022, 15 (16)
[7]   Unsteady Flow Visualization at Part-Load Conditions of a Radial Diffuser Pump: by PIV and CFD [J].
Feng, J. ;
Benra, F. K. ;
Dohmen, H. J. .
JOURNAL OF VISUALIZATION, 2009, 12 (01) :65-72
[8]   Investigation of Periodically Unsteady Flow in a Radial Pump by CFD Simulations and LDV Measurements [J].
Feng, Jianjun ;
Benra, Friedrich-Karl ;
Dohmen, Hans Josef .
JOURNAL OF TURBOMACHINERY-TRANSACTIONS OF THE ASME, 2011, 133 (01)
[9]   Numerical simulation and experimental study of transient characteristics in an axial flow pump during start-up [J].
Fu, Shifeng ;
Zheng, Yuan ;
Kan, Kan ;
Chen, Huixiang ;
Han, Xingxing ;
Liang, Xiaoling ;
Liu, Huiwen ;
Tian, Xiaoqing .
RENEWABLE ENERGY, 2020, 146 :1879-1887
[10]   Analysis of reactor coolant pump transient performance in primary coolant system during start-up period [J].
Gao, Hong ;
Gao, Feng ;
Zhao, Xianchao ;
Chen, Jie ;
Cao, Xuewu .
ANNALS OF NUCLEAR ENERGY, 2013, 54 :202-208