Advanced two-phase instrumentation program. Quarterly progress report, July-September 1981. [PWR]

Technical Report · Fri Jan 01 04:00:00 EST 1982

OSTI ID:5647846

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

The performance of the Westinghouse Reactor Vessel Level Indicating System (RVLIS) in the S-UT-3 test (a communicative break in the cold leg of Semiscale) was analyzed. The Westinghouse RVLIS gave similar indications to Semiscale Test Facility instrumentation measuring the same phenomena (differential pressure (dP)) over equal spans. The Westinghouse measurement is apparently conservative when compared with the two-phase froth level. These dP measurements appear to be nonconservative estimates of level, however, when the measurement system spans the upper core support plate. Level measurement errors of up to 150 cm (60 in.) were observed during S-UT-3. Westinghouse claims that these differences are caused by differences between Semiscale and Westinghouse Reactors. A recommendation for resolving these differences is made.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5647846
• Report Number(s): NUREG/CR-2204-Vol.3; ORNL/TM-8162; ON: DE82005655
• 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
ACCURACY
CONTAINERS
DENSITOMETERS
FLUID FLOW
LEVEL INDICATORS
MEASURING INSTRUMENTS
PERFORMANCE TESTING
PHOTOMETERS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR INSTRUMENTATION
REACTORS
TEST FACILITIES
TESTING
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS