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YAN Ming-yu1,2, QIU Sui-zheng1'2, TIAN Wen-xi2, WANG Jia-qiang2, JIA Dou-nan1'2, LU Dong-hua3 (1. State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049. China; 2. Department of Nuclear and Thermal Power Engineering, Xi'an Jiaotong University, Xi'a. Experimental Investigation on Subcooled Boiling Heat Transfer in a Vertical Double-face Heated Narrow Annulus[J]. Atomic Energy Science and Technology, 2005, 39(2): 143-143. DOI: 10.7538/yzk.2005.39.02.0143
Citation: YAN Ming-yu1,2, QIU Sui-zheng1'2, TIAN Wen-xi2, WANG Jia-qiang2, JIA Dou-nan1'2, LU Dong-hua3 (1. State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049. China; 2. Department of Nuclear and Thermal Power Engineering, Xi'an Jiaotong University, Xi'a. Experimental Investigation on Subcooled Boiling Heat Transfer in a Vertical Double-face Heated Narrow Annulus[J]. Atomic Energy Science and Technology, 2005, 39(2): 143-143. DOI: 10.7538/yzk.2005.39.02.0143
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  • Experimental investigation on the subcooled boiling heat transfer was carried out in a vertical up-flow double narrow annulus with 1. 5 mm gap. The working fluid is deionized water. The ranges of parameters as follows: pressure 0. 84-6. 09 MPa, mass flux 41. 9-300. 2 kg/(m2? s), heat flux 2. 61-114. 41 kW/m2. An empiric correlation used to predict the heat transfer of subcooled boiling in narrow annulus is induced from the experimental data.
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