Thermal hydraulic characteristics of liquid sodium flowing in an annulus are experimentally studied. The annulus is 1100 mm in length, 6 mm as inside diameter and 10 mm as outside diameter. The heat flux in the experiment is from 50 to 210 kW/m2, with Re number from 0 to 18000 and average fluid temperature from 200 °C to 500 °C. Experimental data show that the flow regime of liquid sodium flowing in the annulus can be divided into three regions including laminar flow (Re<2000), transition flow (2000<Re<4000) and turbulent flow (Re>4000). The effects of heat flux, Re number and average fluid temperature of the test section on the heat transfer coefficient are investigated separately. For different regions, correlations for the friction coefficient and for the Nu number are obtained from the experimental data.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4590-5
PROCEEDINGS PAPER
Experimental Study on the Thermal Hydraulic Characteristics of Liquid Sodium Flowing in an Annulus
Zicheng Qiu,
Zicheng Qiu
Xi’an Jiaotong University, Xi’an, Shannxi, China
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Zaiyong Ma,
Zaiyong Ma
Xi’an Jiaotong University, Xi’an, Shannxi, China
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Suizheng Qiu,
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, Shannxi, China
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Yingwei Wu,
Yingwei Wu
Xi’an Jiaotong University, Xi’an, Shannxi, China
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Guanghui Su
Guanghui Su
Xi’an Jiaotong University, Xi’an, Shannxi, China
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Zicheng Qiu
Xi’an Jiaotong University, Xi’an, Shannxi, China
Zaiyong Ma
Xi’an Jiaotong University, Xi’an, Shannxi, China
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, Shannxi, China
Yingwei Wu
Xi’an Jiaotong University, Xi’an, Shannxi, China
Guanghui Su
Xi’an Jiaotong University, Xi’an, Shannxi, China
Paper No:
ICONE22-30244, V02AT09A025; 9 pages
Published Online:
November 17, 2014
Citation
Qiu, Z, Ma, Z, Qiu, S, Wu, Y, & Su, G. "Experimental Study on the Thermal Hydraulic Characteristics of Liquid Sodium Flowing in an Annulus." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 2A: Thermal Hydraulics. Prague, Czech Republic. July 7–11, 2014. V02AT09A025. ASME. https://doi.org/10.1115/ICONE22-30244
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