Nonequilibrium vapor generation rates of flashing water flows

Conference · Tue Jan 01 00:00:00 EST 1980

OSTI ID:5338037

Abuaf, N; Wu, B J.C.; Zimmer, G A; Saha, P; Jones, Jr, O C

A steady water loop with well controlled flow and thermodynamic conditions was designed, built, and made operational for the measurement of the net vapor generation rates under nonequilibrium flashing flow conditions. The test section consists of a converging-diverging nozzle with 49 pressure taps and observation windows at the exit. Pressure distributions and photographic observations were recorded under various flashing conditions. The effect of the various parameters such as inlet pressure, inlet temperature, mass flux, and back pressure on the pressure distributions and flashing regimes was investigated. For flashing under high back pressures, a sharp increase in pressure (condensation shock) was observed in the diverging section. With lower back pressures, although the pressure distributions in the converging section followed the single phase calibration data, the pressure remained constant all along the diverging section of the nozzle. With ..gamma..-densitometry, the diametrical-averaged void fractions were measured along the centerline axis of the test section under various flashing conditions and are reported herein. The measured pressure distributions were combined with the centerline axial void fraction profiles to calculate the volumetric vapor generation rates under nonequilibrium conditions. 19 refs., 13 figs.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5338037
• Report Number(s): BNL-NUREG-27086; CONF-801002-12; ON: TI85018233
• Resource Relation: Conference: ANS/ASME topical meeting on reactor thermal-hydraulics, Saratoga, NY, USA, 9 Oct 1980
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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LOSS OF COOLANT
FLASHING
HEAT TRANSFER
TWO-PHASE FLOW
PWR TYPE REACTORS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
CRITICAL FLOW
DEPRESSURIZATION
FLOW RATE
NOZZLES
REACTOR CORES
REACTOR SAFETY EXPERIMENTS
TUBES
ACCIDENTS
ENERGY TRANSFER
EVAPORATION
FLUID FLOW
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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210100 - Power Reactors
Nonbreeding
Light-Water Moderated
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210200 - Power Reactors
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Nonboiling Water Cooled