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D. J. Kowalski, V. J. Esposito
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 536-539
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32363
Articles are hosted by Taylor and Francis Online.
The classical manner of analyzing the loss-of-coolant accident hydraulic loads imposed on a Westinghouse-type steam generator was to assume a primary side outlet break and to assume that the confining structure was rigid. By considering the vertical divider plate to be flexible, it can be shown that the applied hydraulic forces on the divider plate, tubesheet, and tubes are significantly reduced. The assumption of a flexible divider plate requires the interaction of the fluid and structure simultaneously. The MULTIFLEX computer program and system model have the capability of considering this mutual interaction. Results have been obtained showing the reasons why and how the hydraulic loads on the steam generator internals are attenuated.