Abstract
A quasi-automated high heat flux flow boiling facility has been developed for the systematic study of critical heat flux (CHF), heat transfer, and two-phase pressure drop. High heat flux research is important in state-of-the-art electronics and fusion component design. For fusion applications, there are practically no low-pressure data for large values of coolant channel length-to-diameter (L/D) ratio (i.e., 100), channel diameters near 1.0 cm, and medium to high heat flux levels (i.e., 100 to 2000 W/cm/sup 2/). A second step is provided to fill this void. Forced flow boiling (with water) quasi-steady experiments have been conducted on uniformly (resistively) heated horizontal copper tubes. The tubes were 1.02 cm in inside diameter and 117.87 cm long. The inlet water temperature was 20/sup 0/C. For a 1.6-MPa exit pressure, measurements of the CHF varied from the annular flow regime (150 W/cm/sup 2/) to the subcooled flow boiling water regime (425 W/cm/sup 2/). The mass velocity was varied form 0.63 to 3.5 Mg/m/sup 2/ . s. At 1.6 MPa, the transition between the annular and subcooled CHF regimes were measured to occur between 1.03 and 1.26 Mg/m/sup 2/ . s. Large axial variations in the Nusselt number were also measured.
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