Heat Transfer For Subcooled Flow Boiling In Hypervapotron Configuration

Conference · Sat Jul 01 04:00:00 EDT 2006

OSTI ID:21016413

Chena, Peipei; Wua, Wen; Jonesa, Barclay G ^[1]; Newell, Ty A ^[2]

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1. Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois at Urbana Champaign Urbana, IL, 61801 (United States)
2. Mechanical and Industrial Engineering, University of Illinois at Urbana Champaign Urbana, IL, 61801 (United States)

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 of about 2.96 (q{sup {approx}} {delta}{sub sat} {sup 2}.{sup 96}), which shows good agreement with Bjorge's recognition 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 (NVG) to the fully developed boiling region with acceptable accuracy. However, the heat transfer curve shows a significant deviation when subcooled boiling approaches CHF. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21016413
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
CONFIGURATION
CORRELATIONS
CRITICAL HEAT FLUX
DIAGRAMS
HEAT TRANSFER
REFRIGERANTS
SUBCOOLED BOILING
VAPORS
WATER