Subcooled Water Flow Boiling Transition and theL/DEffect on CHF for a Horizontal Uniformly Heated Tube
- 1 September 1990
- journal article
- research article
- Published by Taylor & Francis in Fusion Technology
- Vol. 18 (2) , 317-324
- https://doi.org/10.13182/fst90-a29303
Abstract
Steady-State subcooled water flow boiling experiments were carried out in a uniformly heated horizontal circular channel with a 0.45-MPa exit pressure and with the mass velocity varying from 1.56 to 8.55 Mg/m2·s. Measurements of critical heat flux (CHF), local heat transfer, and pressure drop were made for a smooth-wall 1.02-cm-diam copper test section with a heated length-to-diameter (L/D) ratio of 49.0. For the same inlet temperature near 20.0°C, comparisons are made with previous data with L/D = 33.0, from 30.0 to 50.0, 96.6 (two cases), and 115.5. The exit pressures for the above data are 0.1, 0.45, 0.77, 1.59, and 1.67 MPa, respectively. When L/D is between 49.0 and 115.5, the L/D influence on CHF is found to be significant for a 1.02-cm channel diameter in subcooled flows for mass velocities above 4.0 Mg/m2·s. This finding is important since most researchers and designers assume minimal L/D influence when L/D is >30. Further, the present CHF and local heat transfer data extend the data base (CHF near 1000.0 W/cm2 and heat transfer coefficient near 70 000 W/m2·K) for large channel diameters near 1.0 cm and low exit pressures. These results will assist in preventing catastrophic conditions from occurring in future systems where the L/D influence might inappropriately be neglected. Finally, Gambill’s correlation predicts CHF significantly above the present data for CHF below 500 W/cm2. Above 500 W/cm2, however, his correlation agreed well with both the present data and the data for L/D = 96.6.Keywords
This publication has 7 references indexed in Scilit:
- Subcooled Water Flow Boiling at 1.66 MPa under Uniform High Heat Flux ConditionsFusion Technology, 1989
- A Model for Diffusion in the Tokamak Edge and Application to the Modular Pump Limiters on Tore SupraFusion Technology, 1988
- Consideration of the Magnetic Field Ripple in the Design of Plasma Edge Components for Tore SupraFusion Technology, 1988
- Heat Transfer for Fusion Component ApplicationsFusion Technology, 1988
- Subcooled Water Flow Boiling Experiments under Uniform High Heat Flux ConditionsFusion Technology, 1988
- Subcooled Flow Boiling Critical Heat Flux (CHF) and Its Application to Fusion Energy Components. Part I. A Review of Fundamentals of CHF and Related Data BaseFusion Technology, 1985
- Subcooled Flow Boiling Critical Heat Flux (CHF) and Its Application to Fusion Energy Components. Part II. A Review of Microconvective, Experimental, and Correlational AspectsFusion Technology, 1985