Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2006, Vol. 17 ›› Issue (3): 177 doi: 10.1016/S1001-8042(06)60034-1

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Experimental research on heat transfer to liquid sodium and its incipient boiling wall superheat in an annulus

XIAO Ze-Jun1,2,* ZHANG Gui-Qin2 SHAN Jian-Qiang2 BAI Xue-Song1 JIA Dou-Nan2   

  1. 1National Key Laboratory of Bubble Physics & Natural Circulation, Nuclear Power Institute of China, Chengdu 610041, China;
    2School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China
XIAO Ze-Jun ZHANG Gui-Qin SHAN Jian-Qiang BAI Xue-Song JIA Dou-Nan. Experimental research on heat transfer to liquid sodium and its incipient boiling wall superheat in an annulus.Nuclear Science and Techniques, 2006, 17(3): 177     doi: 10.1016/S1001-8042(06)60034-1
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Abstract: Liquid sodium is mainly used as a cooling fluid in the liquid metal fast breeder reactor (LMFBR), whose heat transfer, whether convective heat transfer or boiling heat transfer, is different from that of water. So it is impor-tant for both normal and accidental operations of LMFBR to perform experimental research on heat transfer to liquid sodium and its boiling heat transfer. This study deals with heat transfer with high temperature (300–700°C) and low Pe number (20~70) and heat transfer with low temperature (250~270°C) and high Pe number (125~860), and its in-cipient boiling wall superheat in an annulus. Research on heat transfer involves theoretical research and experiments on heat transfer to liquid sodium. It also focuses on the theoretical analysis and experimental research on its incipient boiling wall superheat at positive pressure in an annulus. Semiempirical correlations were obtained and they were well coincident with the experimental data.

Key words: Liquid sodium, Heat transfer, Incipient boiling, Wall superheat, Annulus