Two-phase-flow characteristics during controlled oscillation reflooding of a hot vertical tube. Final report. [PWR]
Technical Report
·
OSTI ID:6276722
Reflooding experiments have been performed to determine the transient void fraction in a heated vertical tube under oscillatory inlet flow conditions. Oscillations of various amplitudes and periods were superimposed on a constant feed rate and measurements were made of temperatures, void fraction, and mass carryover. For experiments with high coolant feed rates, large oscillations were observed in the void fraction, wall temperature, and heat transfer, indicating periodic changes in flow regime near the quench front. For experiments with low coolant feed rates, inlet flow conditions had much less effect on the measured parameters, especially at the upper elevations. The amount of liquid in the test section during these forced oscillation tests was lower than in the constant-injection rate tests due to increased droplet entrainment. This resulted in delayed quenching.
- Research Organization:
- California Univ., Berkeley (USA). Dept. of Nuclear Engineering
- OSTI ID:
- 6276722
- Report Number(s):
- EPRI-NP-2821; ON: DE83902307
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
TWO-PHASE FLOW
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
TWO-PHASE FLOW
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS