BASIC EXPERIMENTAL STUDIES OF BOILING FLUID FLOW AND HEAT TRANSFER AT ELEVATED PRESSURES. Monthly Progress Report, December 1962
Technical Report
·
OSTI ID:4733680
Twenty-four instrumented burnout points and one intentional physical burnout run are reported for a composite tubular geometry (inner heater tube M = 1.478 in. outer heater tube OD = 2.085 in., housing tube ID = 2.90 in. and heated length = 77 in.) with vertical upflow of boiling water at 1000 psia. The ranges of variables studied were: average mass velocities from 0.5 to 2.0 x 10/sup 6/ lb/ hr-ft/sup 2/, average exit conditions from 14 deg F subcooled to 29% steam quality and average instrumented burnout heat fluxes as high as 0.96 x 10/sup 6/ Btu/hr-ft/sup 2/. As in previous burnout tests with the tubular geometry a very strong reverse mass velocity effect was observed in the data. Contrary to the expected performance in all cases burnout was reached first in the inner channel. At low total flow rates (less than about 50 GPM) and high heat fluxes (above approximately 600,000 Btu/hr-ft/sup 2/) a region of test section pressure fluctuations was abruptly encountered during several runs. The transition in and out of this region appeared to follow a line of zero average exit quality. (auth)
- Research Organization:
- Columbia Univ., New York. Engineering Research Labs.
- NSA Number:
- NSA-17-008328
- OSTI ID:
- 4733680
- Report Number(s):
- TID-17702; MPR-XIII-12-62
- Country of Publication:
- United States
- Language:
- English
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OSTI ID:4040392
Related Subjects
BOILING
BURNOUT
CONFERENCE
CONFIGURATION
CONTAMINATION
COOLANT LOOPS
EFFICIENCY
ENGINEERING AND EQUIPMENT
EQUATIONS
FAILURES
FISSION PRODUCTS
FLUID FLOW
FUEL ELEMENTS
GAS COOLANT
HEAT TRANSFER
HIGH TEMPERATURE
IMPURITIES
INSTRUMENTS
LABORATORY EQUIPMENT
LATTICES
LEAKS
LOW TEMPERATURE
MASS
MEASURED VALUES
MOCKUP
NEUTRON FLUX
OXIDATION
OXYGEN
PERFORMANCE
PHASE DIAGRAMS
POWER PLANTS
PRESSURE
RADIATION EFFECTS
RADIATION PROTECTION
RADIOACTIVITY
RADIOISOTOPES
REACTION KINETICS
REACTOR SAFETY
STABILITY
STEAM
STEAM QUALITY
TEMPERATURE
TOKAI-MURA
TUBES
URANIUM
URANIUM DIOXIDE
URANIUM TRIOXIDE
VELOCITY
WATER
BURNOUT
CONFERENCE
CONFIGURATION
CONTAMINATION
COOLANT LOOPS
EFFICIENCY
ENGINEERING AND EQUIPMENT
EQUATIONS
FAILURES
FISSION PRODUCTS
FLUID FLOW
FUEL ELEMENTS
GAS COOLANT
HEAT TRANSFER
HIGH TEMPERATURE
IMPURITIES
INSTRUMENTS
LABORATORY EQUIPMENT
LATTICES
LEAKS
LOW TEMPERATURE
MASS
MEASURED VALUES
MOCKUP
NEUTRON FLUX
OXIDATION
OXYGEN
PERFORMANCE
PHASE DIAGRAMS
POWER PLANTS
PRESSURE
RADIATION EFFECTS
RADIATION PROTECTION
RADIOACTIVITY
RADIOISOTOPES
REACTION KINETICS
REACTOR SAFETY
STABILITY
STEAM
STEAM QUALITY
TEMPERATURE
TOKAI-MURA
TUBES
URANIUM
URANIUM DIOXIDE
URANIUM TRIOXIDE
VELOCITY
WATER