Two-phase-flow characteristics during reflooding of a hot vertical tube. Final report. [PWR]
Technical Report
·
OSTI ID:6317407
Experiments have been performed to measure transient void fraction histories during reflooding of a hot vertical tube. This report describes the constant-injection bottom-reflood experimental program and its results, including void fraction measurements made with a gamma densitometer. These data show different void fraction profiles for the two flow regimes observed at the quench front - inverted-annular and annular flow.
- Research Organization:
- California Univ., Santa Barbara (USA). Dept. of Chemical and Nuclear Engineering
- OSTI ID:
- 6317407
- Report Number(s):
- EPRI-NP-2820; ON: DE83901900
- Country of Publication:
- United States
- Language:
- English
Similar Records
Two-phase-flow characteristics during controlled oscillation reflooding of a hot vertical tube. Final report. [PWR]
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Sun May 01 00:00:00 EDT 1983
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Transient non-equilibrium two-phase flow: reflooding of a vertical flow channel
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Transient non-equilibrium two-phase flow: reflooding of a heated vertical tube under controlled oscillation inlet flow conditions
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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 MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE DISTRIBUTION
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 MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE DISTRIBUTION
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS