期刊
JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME
卷 137, 期 5, 页码 -出版社
ASME
DOI: 10.1115/1.4029593
关键词
wall nucleation; bubble departure diameter; bubble departure frequency; subcooled boiling; annulus; heat transfer
资金
- Department of Energy Nuclear Energy University Program Graduate Fellowship
Wall nucleation experiments have been performed in a vertical annulus test section for investigation of the bubble departure diameter and bubble departure frequency. The experimental data in forced convective subcooled boiling flow is presented as a parametric study of the effect of wall heat flux, local bulk liquid subcooling, liquid flow rate, and system pressure. The data are shown to extend the database currently available in literature to a wider range of system conditions. Along with the current database in forced convective flow, the available models for bubble departure size and frequency are reviewed and compared with the existing database. The prediction of the bubble departure frequency is shown to require accurate modeling of the bubble departure diameter which has poor agreement with the experimental database.
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