SINGLE- AND TWO-PHASE HEAT TRANSFER TO NEAR CRITICAL WATER UNDER FORCED CONVECTION IN AN ELECTRICALLY HEATED VERTICAL TUBE (thesis). Technical Report No. 14
Technical Report
·
OSTI ID:4032823
Results of an experimental investigation of heat transfer to water in turbulent flow at high pressures are presented. The experimental apparatus was a closed circuit, forced convection wnter loop. The test section was a vertical, electrically heated stainless steel tube approximately four feet in length, 1/2 inch in diameter with a nominal wall thickness of 1/16 inch. In the investigation, carried out at pressures between 2560 and 3200 psia, the mass flux was varied between 1.5 x 10/sup 6/ and 2.9 x 10/sup 6/ lb/hr ft/sup 2/, the applied heat flux was varied between 113,700 and 398,100 B/hr ft/sup 2/, bulk water temperatures ranged from 606 deg F to saturation temperathres, and the Reynolds number in the test section varied between 207,000 and 475,000. Local property values, heat transfer parameters and selected dimensionless ratios were computed for each of thirteen positions along the lengih of the test section. Heat transfer coefficients, based on bulk fluid temperature, were found to range from 6500 to 53,000 B/hr ft/sup 2/ F, and reached a peak of 107,000 B/hr ft/sup 2/ F at the transition poirt in a two phase film boiling run. It was found that all single phase subcooled heat transfer data could be successfully correlated, in turn, by the well known Dittus-Boelter, SiederTate, Colburn and Prandtl equations. An empirical correlation equation, developed from the Prandti equation, successfully correlated the experimental subcooled single phase, subcooled boiling, and low quality nucleate boiling data. (P.C.H.)
- Research Organization:
- Purdue Research Foundation, Lafayette, Ind.
- NSA Number:
- NSA-18-018002
- OSTI ID:
- 4032823
- Report Number(s):
- TID-20407
- Country of Publication:
- United States
- Language:
- English
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