FLOW STABILITY LOOP--NUCLEATE BOILING HEAT TRANSFER WITH SANTOWAX R
Technical Report
·
OSTI ID:4689990
Santowax R forced convection boiling heat transfer experiments were conducted using the Flow Stability Loop. The test section (a 12 ft long, 9/16 in. OD, 0.042 in. wall thickness, nickel tube) and instrumentation were the same as used in previous experiments with this loop. Results were compared with the nucleate boiling heat transfer model used in FUGUE, Levy's generalized boiling heat transfer equation. An experimental correlation coefficient, B/sub L/, was determined as a function of pressure. Good agreement was obtained between the experimental temperature differences and the values calculated with the Levy equation using the experimental correlation coefficient. The following ranges of the variables were studied: heat flux, 30,000 to 110,000 Btu/hr ft/sup 2/; coolant velocity, 5 to 14 ft/sec; outlet pressure, 15 to 26 psia; wall superheat, 42 to 73 un. Concent 85% F; and coolant subcooling, 0 to 24 un. Concent 85% F. In all cases the experimental and calculated wall superheat temperatures agreed within 5 un. Concent 85% F. (auth)
- Research Organization:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- DOE Contract Number:
- AT(11-1)-GEN-8
- NSA Number:
- NSA-17-023477
- OSTI ID:
- 4689990
- Report Number(s):
- NAA-SR-Memo-7418
- Country of Publication:
- United States
- Language:
- English
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