Heat transfer for subcooled flow boiling in hypervapotron configuration

被引:3
作者
Chen, Peipei [1 ]
Wu, Wen [1 ]
Jones, Barclay G. [1 ]
Newell, Ty A. [2 ]
机构
[1] Univ Illinois, Dept Nucl Plasma & Radiol Engn, Tilbot Lab 216, Urbana, IL 61801 USA
[2] Univ Illinois, Dept Mech Sci & Engn, Urbana, IL 61801 USA
关键词
subcooled boiling; critical heat flux; hypervapotron;
D O I
10.13182/NT08-A4010
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This work reports on experimental studies that examine subcooled boiling on the enhanced heat transfer surface of hypervapotron structures. The use of simulant fluid (refrigerant R134a) instead of prototypic water allows examination of a full range of subcooled boiling, including up to critical heat flux (CHF). The experimental results are compared to Bjorge's model and Kandlikar's heat transfer correlation in the subcooled boiling region. It is found that the fully developed boiling curve has a slope relation of similar to 2.96(q" similar to Delta T-sat(2.96)), which shows good agreement with Bjorge's correlation for flat surface channels. In addition, Kandlikar's correlation is also able to predict the heat transfer coefficient for the range from net vapor generation to the fully developed boiling region with acceptable accuracy. However, the heat transfer curve shows a significant deviation when subcooled boiling approaches CHF.
引用
收藏
页码:89 / 96
页数:8
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