Advanced two-phase flow instrumentation program. Quarterly progress report, January-March 1982. [PWR]

Technical Report · Thu Jul 01 04:00:00 EDT 1982

OSTI ID:5239064

Hardy, J E; Rogers, S C; Miller, G N; Zabriskie, W L

The performance of the Westinghouse Reactor Vessel Level Indicating System (RVLIS) was analyzed for a series of tests in the Semiscale Test Facility. A summary of the results and conclusions from those small-break simulation experiments is presented. The Westinghouse RVLIS indicated a level measurement that was lower than the vessel coolant level for all tests. The RVLIS indication was at times higher than the vessel collapsed liquid level. This discrepancy was apparently created by structural differences in the Semiscale facility and a Westinghouse pressurized-water reactor (PWR). Modifications were made to Semiscale to better simulate a Westinghouse PWR, and a retest was completed. The RVLIS measurements showed much better agreement with the vessel collapsed liquid level for this retest. In addition to the RVLIS analysis, an ultrasonic sensor is being developed to measure simultaneously the level, temperature, and density of the fluid in which it is immersed.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5239064
• Report Number(s): NUREG/CR-2752-Vol.1; ORNL/TM-8365; ON: DE82017253
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACOUSTIC TESTING
CONTAINERS
FLUID FLOW
LEVEL INDICATORS
MATERIALS TESTING
MEASURING INSTRUMENTS
NONDESTRUCTIVE TESTING
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR INSTRUMENTATION
REACTORS
TESTING
TWO-PHASE FLOW
ULTRASONIC TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS