Abstract
It is now mandatory to seismically qualify the safety-related structures and components used in the nuclear power plants. Among several qualification approaches the qualification by the analysis using finite element (FE) method is the most common approach used in practice. However, the estimated dynamic behaviour by FE model of a structure is known to show significant deviations from the dynamic behaviour of the 'as-installed' structure in many cases. Considering such limitations, few researchers have advocated re-qualification of such structures after their installation at site to enhance the confidence in qualification vis-à-vis plant safety. For such an exercise, validation of FE model with experimental modal data is important. A validated FE model can be obtained by the model updating methods in conjugation with the in situ experimental modal data. Such a model can then be used for qualification. However, for the reactor in-core components such a modal testing and FE model updating may not be straightforward. Hence, the complication involved in the reliable seismic qualification of in-core components and the advantage of using the FE model updating has been brought out in the paper through an example of a typical in-core component - a perforated horizontal tube recently installed in a nuclear reactor in India. © 2005 Elsevier B.V. All rights reserved.
Original language | English |
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Pages (from-to) | 232-237 |
Number of pages | 5 |
Journal | Nuclear Engineering and Design |
Volume | 236 |
Issue number | 3 |
DOIs | |
Publication status | Published - Feb 2006 |