Critical Heat Fluxes of Subcooled Water Flow Boiling Against Outlet Subcooling in Short Vertical Tube
- Department of Energy Science and Technology, Kyoto University, Uji 611-0011 (Japan)
- National Institute for Fusion Science, Toki 509-5292 (Japan)
The critical heat fluxes (CHFs) of subcooled water flow boiling are systematically measured for the flow velocities (u=4.0 to 13.3 m/s), the outlet sub-cooling ({delta}T{sub sub,out}=3 to 129 K) and the outlet pressure (P{sub out}=800 kPa). The SUS304 test tubes of 3, 6, 9 and 12 mm in inner-diameter, d, and 33, 66, 99 and 133 mm in length, L, respectively for L/d=11 are used. The CHFs first become lower and then become higher with the increase in subcooling. The CHFs for four different inner-diameters with L/d=11 measured here become higher with the decrease in the diameter. CHF correlation for the latter increasing regime was given in non-dimensional form against average outlet sub-cooling based on the experimental data. The correlation can describe not only the CHFs obtained in this work at the outlet pressure of 800 kPa but also the authors' published CHFs (1284 points) for the wide range of P{sub out}=159 kPa to 1 MPa, d=6, 9 and 12 mm, L=49, 99 and 149 mm, {delta}T{sub sub,out}=-4 to 130 K and u=4.0 to 13.3 m/s within 15 % difference for 50 K{delta}T{sub sub,out}130 K and within +30 to -10 % for 30 K<{delta}T{sub sub,out}<50 K. (authors)
- Research Organization:
- The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
- OSTI ID:
- 21072821
- Resource Relation:
- Conference: ICONE-10: 10. international conference on nuclear engineering, Arlington - Virginia (United States), 14-18 Apr 2002; Other Information: Country of input: France
- Country of Publication:
- United States
- Language:
- English
Similar Records
A Procedure to Predict Subcooled-Water-Flow-Boiling CHF in Uniformly Heated Tubes for High-Heat-Flux Applications
A New Facility for Measurements of Three-Dimensional, Local Subcooled Flow Boiling Heat Flux and Related Critical Heat Flux for PFCs