Test data report on Westinghouse Reactor Vessel Level Indicating System performance during Semiscale Tests S-UT-4 and S-UT-5

Technical Report · Tue Sep 01 04:00:00 EDT 1981

OSTI ID:5630315

Tingle, W W

The Westinghouse Reactor Vessel Level Indicating System (RVLIS) has been installed on the Semiscale Mod-2A system to test its operation during a series of small break experiments. These experiments (S-UT-4 and S-UT-5) are the fourth and fifth experiments in the upper head injection test series to be performed on the Semiscale Mod-2A system and the second and third in which the Westinghouse RVLIS has been installed for testing. These experiments were conducted to simulate 2-1/2% communicative breaks in the cold leg of a pressurized water reactor (PWR). Initial conditions of these experiments were typical of, or scaled from, an upper head injection (UHI) plant. These experiments were similar, the difference being that UHI was used in S-UT-5, but not on S-UT-4. These experiments used external heaters on both primary coolant system loops to compensate for external heat losses, otherwise S-UT-4 was identical to S-UT-3, the first experiment in which a report on the RVLIS was issued. The principal objective of these experiments was to investigate the effect of UHI on system thermal-hydraulic response during a 2-1/2% cold leg communicative break. The liquid levels in the core and upper head were monitored by normal Semiscale ..delta..P and density instrumentation to provide a basis for comparison with the Westinghouse system data.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5630315
• Report Number(s): EGG-SEMI-5552; ON: TI85013924
• Country of Publication: United States
• Language: English

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