Heat transfer above the two-phase mixture level under core uncovery conditions in a 336-rod bundle. [PWR]

Technical Report · Thu Jan 01 04:00:00 EST 1981

DOI:https://doi.org/10.2172/6880276· OSTI ID:6880276

Andreychek, T. S.

Twenty-two constant pressure boiloff, or core uncovery, tests were performed in the G-2 Loop test facility using a bundle of 336 heater rods. The parameters tested were vessel pressure and bundle power. For each test, temperatures at various axial positions within selected heater rods in the bundle and temperatures, pressures, differential pressures, and water levels at various locations around the facility were taken and recorded. From the recorded data were calculated heater rod heat fluxes, steam flows, liquid carryover from the bundle, and rates of boiloff or core uncovery. These calculated data were used to evaluate the heat transfer process above the bundle two-phase mixture level under core uncovery conditions.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div.
• OSTI ID: 6880276
• Report Number(s): EPRI-NP-1692(Vol.2)
• Country of Publication: United States
• Language: English

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ACCIDENTS
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WATER COOLED REACTORS
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