Advanced two-phase flow instrumentation program. Quarterly progress report, October to December 1981

Technical Report · Mon Mar 01 04:00:00 EST 1982

OSTI ID:5562917

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

The performance of the Westinghouse Reactor Vessel Level Indicating System (RVLIS) during tests S-UT-6 and S-UT-7 (5% cold-leg breaks in the Semiscale Test Facility) was analyzed. The RVLIS, a system employing differential pressure (dP) cells, gave estimates of vessel level similar to those of Semiscale level instrumentation when measuring over equal spans. These RVLIS measurements are conservative to vessel coolant levels for both S-UT-6 and S-UT-7. At times, the RVLIS indications are greater than the vessel collapsed liquid level measured by Semiscale instrumentation. During S-UT-6, level estimate differences between RVLIS and Semiscale dPs of up to 215 cm (85 in.) were observed. These discrepancies may be explained by differences in Semiscale and Westinghouse pressurized-water reactor internal designs. Excellent agreement was noted between Semiscale and Westinghouse vessel levels for S-UT-7, an upper-head injection test.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5562917
• Report Number(s): NUREG/CR-2204(Vol.4); ORNL/TM-8231; ON: DE82009151
• 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
FLOWMETERS
FLUID FLOW
LEVEL INDICATORS
MEASURING INSTRUMENTS
METERS
PWR TYPE REACTORS
REACTOR INSTRUMENTATION
REACTORS
TEST FACILITIES
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS