Experimental investigation of a flow monitoring instrument in an upper plenum of an air-water reflood test facility. [PWR]
Conference
·
OSTI ID:5206594
Instrumentation was developed for measuring fluid phenomena in the upper plenum of pressurized water reactor reflood facilities. In particular, the instrumentation measured two-phase flow velocity and void fraction. The principle of operation of the instrumentation scheme was based on the measurement of electrical impedance. The technique of analysis of random signals from two spatially separated impedance sensors was employed to measure two-phase flow velocity. A relative admittance technique was used to determine void fraction. The performance of the instrumentaton was studied in an air-water test facility.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5206594
- Report Number(s):
- CONF-800804-26
- Country of Publication:
- United States
- Language:
- English
Similar Records
Development of in-vessel reflood instrumentation at ORNL. [PWR]
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Conference
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Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:6069174
Reflood instrumentation development at ORNL: a status report
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6348393
Two-phase flow measurement in the upper plenum of a PWR during reflood
Technical Report
·
Fri Aug 01 00:00:00 EDT 1986
·
OSTI ID:5290902
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
CALIBRATION
FLOWMETERS
FLUID FLOW
LOSS OF COOLANT
MEASURING INSTRUMENTS
PERFORMANCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEST FACILITIES
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
CALIBRATION
FLOWMETERS
FLUID FLOW
LOSS OF COOLANT
MEASURING INSTRUMENTS
PERFORMANCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEST FACILITIES
TWO-PHASE FLOW
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS