Measurement of two-component flow using ultrasonic flowmeters

Conference · Tue Jan 01 00:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5762807

Whitehouse, J C; Eghbali, D A ^[1]; Flitton, V E ^[2]; Anderson, D G ^[3]

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1. Westinghouse Savannah River Co., Aiken, SC (United States)
2. Idaho National Engineering Lab., Idaho Falls (United States)
3. Wyle Labs., Norco, CA (United States)

A novel application of existing ultrasonic flowmeter technology is described. This application was motivated by the need to make nonintrusive measurements of two-component flow in support of reactor safety research at the Savannah River Site (SRS). Two types of ultrasonic flowmeters were used during the test program in 1989. Both types were posttest calibrated in the summer of 1990 in a large gas/water flow facility at Wyle Laboratory in Norco, California. Both flowmeter types were found to measure total volumetric flow over a portion of their ranges accurately. When combined with void fraction measured by a three-beam gamma densitometer system it was possible to determine the individual gas and water flows.

• OSTI ID: 5762807
• Report Number(s): CONF-910603-; CODEN: TANSA
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 63; Conference: Annual meeting of the American Nuclear Society (ANS), Orlando, FL (United States), 2-6 Jun 1991; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
SPECIAL PRODUCTION REACTORS
REACTOR SAFETY
TWO-PHASE FLOW
RESEARCH PROGRAMS
ULTRASONIC TESTING
ACCURACY
CALIBRATION
DENSITOMETERS
FLOW RATE
FLOWMETERS
SAVANNAH RIVER PLANT
TEST FACILITIES
ACOUSTIC TESTING
FLUID FLOW
MATERIALS TESTING
MEASURING INSTRUMENTS
METERS
NATIONAL ORGANIZATIONS
NONDESTRUCTIVE TESTING
PHOTOMETERS
PRODUCTION REACTORS
REACTORS
SAFETY
TESTING
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
420400 - Engineering- Heat Transfer & Fluid Flow