BASIC STUDIES IN HEAT TRANSFER AND FLUID FLOW. Quarterly Progress Report, January 1, 1961 to March 31, 1961
Technical Report
·
OSTI ID:4037502
Nucleate Boiling Heat Transfer. Data collected for tubular nickel heating elements are presented in the form of heat flux density vs surface temperature graphs at constsnt pressure and water velocity. The results indicate that velocity and liquid subcooling variations do not have an appreciable effect on the heat transfer coefficient in subcooled nucleate boiling, but that increasing the pressure level causes the convection-boiling transition in heat transfer to occur at higher surface temperatures. The location of the burnout points suggests that the maximum achievable heat flux density is increased by increased subcooling. Transient Vaporization. Several thin-film heaters were calibrated and the results presented in the form of resistsnce vs temperature graphs. The value of 4000 ohms is chosen as the optimum value for the heater resistances. The appearance of the heaters before and after film and nucleate boiling with hexane was studied. Forced Convection Boiling. A photographic method is presented for determining flow pattern velocities. An analytical method for predicting void fraction and pressure drop for vertical, upward, twophase flow in the bubble flow region is examined, and comparisons between the bubble flow model and experiment are given. Convection Heat Transfer in Non- Circular Ducts. The deviation of experimental heat transfer coefficients for eccentric annuli from those predicted by Stein-Begell concentric equation is ascribed to circumferential temperature variations. Pressure drop runs were made with a 92% eccentric annulus and the data presented in the form of a friction factor vs Reynolds number graph. A method is outlined for predicting the pressure drop in eccentric annuli, and results are presented for 0, 64, and 90% eccentricities. (D.L.C.)
- Research Organization:
- Columbia Univ., New York. Engineering Research Labs.
- NSA Number:
- NSA-15-017057
- OSTI ID:
- 4037502
- Report Number(s):
- NYO-9646; IX-QPR-1-61
- Country of Publication:
- United States
- Language:
- English
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Journal Article
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Tue May 01 00:00:00 EDT 1962
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OSTI ID:4827316
BASIC STUDIES IN HEAT TRANSFER AND FLUID FLOW. Quarterly Progress Report for Period April 1, 1961 to June 30, 1961
Technical Report
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Fri Jun 30 00:00:00 EDT 1961
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OSTI ID:4840750
HEAT TRANSFER AND CRITICAL CONDITIONS IN NUCLEATE BOILING OF SUBCOOLED AND FLOWING LIQUIDS
Technical Report
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Thu Dec 31 23:00:00 EST 1959
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OSTI ID:4136051