PIV measurement and numerical investigation on flow characteristics of simulated fast reactor fuel subassembly

Cheng Zhang; Haoran Ju; Dalin Zhang; Shuijin Wu; Yijun Xu; Yingwei Wu; Suizheng Qiu; G.H. Su

Nuclear Engineering and Technology (May 2020)

PIV measurement and numerical investigation on flow characteristics of simulated fast reactor fuel subassembly

Cheng Zhang,
Haoran Ju,
Dalin Zhang,
Shuijin Wu,
Yijun Xu,
Yingwei Wu,
Suizheng Qiu,
G.H. Su

Affiliations

Cheng Zhang: State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China; China Institute of Atomic Energy, P. O. BOX 275-42, Beijing, 102413, China
Haoran Ju: State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China
Dalin Zhang: State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China; Corresponding author.
Shuijin Wu: China Institute of Atomic Energy, P. O. BOX 275-42, Beijing, 102413, China
Yijun Xu: China Institute of Atomic Energy, P. O. BOX 275-42, Beijing, 102413, China
Yingwei Wu: State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China
Suizheng Qiu: State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China
G.H. Su: State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China

Journal volume & issue: Vol. 52, no. 5
pp. 897 – 907

Abstract

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The flow characteristics of reactor fuel assembly always intrigue the designers and the experimentalists among the myriad phenomena that occur simultaneously in a nuclear core. In this work, the visual experimental method has been developed on the basis of refraction index matching (RIM) and particle image velocimetry (PIV) techniques to investigate the detailed flow characteristics in China fast reactor fuel subassembly. A 7-rod bundle of simulated fuel subassembly was fabricated for fine examination of flow characteristics in different subchannels. The experiments were performed at condition of Re = 6500 (axial bulk velocity 1.6 m/s) and the fluid medium was maintained at 30 °C and 1.0 bar during operation. As for results, axial and lateral flow features were observed. It is shown that the spiral wire has an inhibitory effect on axial flow and significant intensity of lateral flow mixing effect is induced by the wire. The root mean square (RMS) of lateral velocity fluctuation was acquired after data processing, which indicates the strong turbulence characteristics in different flow subchannels. Keywords: Lateral flow mixing strength, PIV measurement, Flow characteristics analysis, China fast reactor fuel subassembly

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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