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Engineering Review of Design Changes in Taiwan Nuclear Plant

During a shutdown of the Kuosheng 1 plant, Taiwan, operation of the LPCI system for normal shutdown caused failure of an LPRM.

Testing by G.E. in their (HF)2 facility duplicated the failure, which has been attributed to flow-induced vibration of the LPRM. G.E. devised a flow-deflector to prevent cross-flow from the LPCI across core components. This deflector had to be installed in Grand Gulf very quickly to avoid delay in fuel loading.

In order to increase assurance that the design, construction, and installation of the deflector plate were proper, Mississippi Power & Light Company asked O’Donnell to review the problem and the proposed solution. We analytically determined that the fatigue usage factor, pump-induced vibration, low-pressure injection system head loss, fluence at welds, and the diaphragm connection of the LPCI line to the shroud were adequate. Subsequent testing confirmed the adequacy.

 

See also:
Development of Elevated Temperature Design Criteria for Nuclear Components
Finite Element Analysis of a Vessel Processing Nuclear Waste

 
Nuclear Power Plant Consulting
Publications – Heat Exchangers, Pressure Vessels, Welds and Other Applications, Fatigue, Elevated Temperature

 

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