Instrumentation for localized measurements in two-phase flow conditions

Conference · Mon Jan 01 04:00:00 EST 1979

OSTI ID:6142464

Neff, G G; Averill, R H; Shurts, S W

Three types of instrumentation that have been developed by EG and G Idaho, Inc., and its predecessor, Aerojet Nuclear company, at the Idaho National Engineering Laboratory to investigate two-phase flow phenomenon in a nuclear reactor at the Loss-of-Fluid Test (LOFT) facility are discussed: (a) a combination drag disc-turbine transducer (DTT), (b) a multibeam nuclear hardened gamma densitometer system, and (c) a conductivity sensitive liquid level transducer (LLT). The DTT obtains data on the complex problem of two-phase flow conditions in the LOFT primary coolant system during a loss-os-coolant experiment (LOCE). The discussion of the DTT describes how a turbine, measuring coolant velocity, and a drag disc, measuring coolant momentum flux, can provide valuable mass flow data. The nuclear hardened gamma densitometer is used to obtain density and flow regime information for two-phase flow in the LOFT primary coolant system during a LOCE. The LLT is used to measure water and steam conditions within the LOFT reactor core during a LOCE. The LLT design and the type of data obtained are described.

• Research Organization: Idaho National Engineering Laboratory (INEL), Idaho Falls, ID (United States)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6142464
• Report Number(s): CONF-790803-15
• Country of Publication: United States
• Language: English

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47 OTHER INSTRUMENTATION
DESIGN
FLOWMETERS
FLUID FLOW
LOFT REACTOR
MEASURING INSTRUMENTS
PWR TYPE REACTORS
REACTOR INSTRUMENTATION
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
TRANSDUCERS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS