Loads on steam generator tubes during simulated loss-of-coolant accident conditions. Final report. [PWR]

Technical Report · Mon Nov 01 04:00:00 EST 1982

OSTI ID:6635088

Guerrero, H N; Hiestand, J W; Rossano, F V; Shah, P K; Thakkar, J G

This report presents the work performed to verify the CEFLASH digital computer code modeling of the hydro-dynamic loads in a steam generator tube during a loss-of-coolant accident (LOCA). The test loop simulated the primary side thermal-hydraulic conditions in an operational nuclear steam generator. The loop consisted of 5 full size double 90/sup 0/ bend tubes and steam generator plena, a pressurizer, a reactor resistance simulator, a heater, a pump, and associated pipes and valves to complete the system. The tubes used were of typical length and the same outside diameter as those used in C-E steam generators. Prototypical supports were provided for the bundle of 5 tubes. Cold leg guillotine breaks were simulated using quick opening valve and rupture disks. Break opening times ranged from less than 1 msec to as much as 67 milliseconds. The loop instrumentation was designed to measure the transient pressure history at various locations and monitor the structural response of the tube to the LOCA hydrodynamic loading. A series of blowdown tests was performed for different operating and boundary conditions. Analytically predicted transient pressure histories and the differential pressure history across the tube span were compared with the experimental data.

• Research Organization: Combustion Engineering, Inc., Chattanooga, TN (USA). Chattanooga Nuclear Operations
• OSTI ID: 6635088
• Report Number(s): EPRI-NP-2652; ON: DE83901126
• Country of Publication: United States
• Language: English

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