Experimental study on phase distribution of low-pressure subcooled boiling flow in vertical circular tube

被引：0
作者：
Bao W. [1 ]
Chen B.-D. [1 ]
Xu J.-J. [1 ]
Xie T.-Z. [1 ]
Huang Y.-P. [1 ]
机构：
[1] CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulic Technology, Nuclear Power Institute of China, Chengdu
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2016年 / 50卷 / 08期
关键词：
Bubble; Optical probe; Rolling condition; Subcooled boiling flow; Void fraction;
D O I：
10.7538/yzk.2016.50.08.1381
中图分类号：
学科分类号：
摘要：
Radial distributions of interfacial parameters including local void fraction, interfacial area concentration and bubble Sauter diameter were measured in low-pressure subcooled boiling flow of water in a vertical circular tube of 24 mm diameter using the double-sensor optical fiber probe. The experimental results show that the phase distribution in vertical circular tube is symmetrical. With heat flux increasing, the local void fraction varies from wall peaking to intermediate peaking, and core peaking can be seen under high heat flux condition. The local void fraction decreases as mass flux increases, and the phase distribution has a transition from intermediate peaking to wall peaking. Further more, it is also found that the local interfacial parameter decreases as pressure increases. © 2016, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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页码：1381 / 1386
页数：5
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