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Modal Analysis of a Nuclear Reactor With Fluid-Structure Interaction: Influence of Fluid Compressibility

[+] Author Affiliations
Jean-François Sigrist

DCN Propulsion, La Montagne, France

Daniel Broc

CEA Saclay, Gif-sur-Yvette, France

Paper No. PVP2006-ICPVT-11-93015, pp. 25-33; 9 pages
  • ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference
  • Volume 4: Fluid Structure Interaction, Parts A and B
  • Vancouver, BC, Canada, July 23–27, 2006
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4755-1 | eISBN: 0-7918-3782-3
  • Copyright © 2006 by ASME


The present paper deals with the modal analysis of a nuclear with fluid-structure interaction effects. In a previous study, added mass and added stiffness effects due to fluid-structure interaction were modeled and studied. A dynamic analysis was performed for a seismic excitation, i.e. in the low frequency range. The present study deals with high frequency analysis, i.e. taking into account compressibility effects in the fluid problem. Elasto-acoustic coupling phenomena are studied and described in the industrial case. The elasto-acoustic coupled problem is formulated using the displacement/pressure-displacement potential coupled formulation which yields symmetric matrices. A modal analysis is first performed on the fluid problem alone, with a calculation of acoustic eigenfrequencies and the corresponding modal masses. A modal analysis is then performed for the coupled fluid-structure problem in the case of an incompressible fluid and a compressible fluid at standard pressure and temperature conditions and for a compressible fluid at the operating pressure and temperature conditions. Elasto-coupling effects are then highlighted and discussed.

Copyright © 2006 by ASME



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