PWR FLECHT SEASET 21-rod-bundle flow-blockage task: data and analysis report. NRC/EPRI/Westinghouse report No. 11, main report and appendices A-J

Technical Report · Wed Sep 01 00:00:00 EDT 1982

DOI:https://doi.org/10.2172/7093767· OSTI ID:7093767

Loftus, M J; Hochreiter, L E; Lee, N; McGuire, M F; Wenzel, A H; Valkovic, M M

This report presents data and limited analysis from the 21-Rod Bundle Flow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Separate Effects and Systems Effects Test Program (FLECHT SEASET). The tests consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. Steam cooling and hydraulic characteristics tests were also conducted. These tests were utilized to determine effects of various flow blockage configurations (shapes and distributions) on reflooding behavior, to aid in development/assessment of computational models in predicting reflooding behavior of flow blockage configurations, and to screen flow blockage configurations for future 163-rod flow blockage bundle tests.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA)
• OSTI ID: 7093767
• Report Number(s): NUREG/CR-2444-Vol.1; EPRI-NP-2014-Vol.1; WCAP-9992-Vol.1; ON: DE83900164
• Country of Publication: United States
• Language: English

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