Analysis of the performance of the Westinghouse reactor vessel level indicating system for tests at semiscale. [PWR]

Technical Report · Fri Oct 01 00:00:00 EDT 1982

DOI:https://doi.org/10.2172/6746261· OSTI ID:6746261

Hardy, J. E.; Miller, G. N.

The Westinghouse Reactor Vessel Level Indicating System (RVLIS), a differential pressure level measurement system, was tested at SEMISCALE. This report contains the analyses of these tests and the conclusions of these analyses. The tests performed included small break and intermediate break tests. Also, frequency response and natural circulation tests were run and analyzed. The RVLIS always indicated a level less than the two phase froth level. The RVLIS output in early small break tests indicated a level 200 cm greater than actual collapsed liquid level. This discrepancy was caused by structural differences between SEMISCALE and a Westinghouse reactor. Once modifications were made so that SEMISCALE better simulated a Westinghouse PWR, the maximum difference between RVLIS and SEMISCALE instrumentation was 30 cm or 3% which is less than the stated uncertainty of the Westinghouse RVLIS.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6746261
• Report Number(s): NUREG/CR-2720; ORNL/TM-8336; ON: DE83001598
• Country of Publication: United States
• Language: English

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TEST FACILITIES
CONTAINERS
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