The present paper is related to a seismic analysis of a naval propulsion ground prototype nuclear reactor with fluid-structure interaction modeling. Many numerical methods have been proposed over the past years to take fluid/structure phenomenon into account [14] in various engineering domains, among which nuclear engineering in seismic analysis [15]. The purpose of the present study is to apply general methods on a global approach of the nuclear reactor. A simplified design of the pressure vessel and the internal structure is presented; fluid-structure interaction is characterized by the following effects: • added mass effects are highlighted with the calculation of an added mass operator, obtained from a finite element discretisation of the coupled problem. The numerical model is developed within the CASTEM code using an axi-symmetric model of the industrial structure; • coupling effects between the external and internal structure via the confined inner fluid are also illustrated and numerically described with the added mass operator; • added stiffness effects are taken into account with an added stiffness matrix describing pre-stress effects due to a static pressure loading simulating the actual operating conditions of the reactor. The expected fluid-structure interaction effects on the nuclear pressure vessel and their numerical modeling leads to the definition of a global coupled model which can be used to perform a seismic analysis. A modal analysis is first performed and classical linear methods (static, spectral and temporal) are then applied on the studied structure with taking fluid-structure into account.
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ASME 2005 Pressure Vessels and Piping Conference
July 17–21, 2005
Denver, Colorado, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4189-8
PROCEEDINGS PAPER
Seismic Analysis of a Nuclear Reactor With Fluid-Structure Interaction
Jean-Franc¸ois Sigrist,
Jean-Franc¸ois Sigrist
DCN Propulsion, La Montagne, France
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Daniel Broc,
Daniel Broc
CEA Saclay, Gif-sur-Yvette, France
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Christian Laine
Christian Laine
DCN Propulsion, La Montagne, France
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Jean-Franc¸ois Sigrist
DCN Propulsion, La Montagne, France
Daniel Broc
CEA Saclay, Gif-sur-Yvette, France
Christian Laine
DCN Propulsion, La Montagne, France
Paper No:
PVP2005-71182, pp. 37-44; 8 pages
Published Online:
July 29, 2008
Citation
Sigrist, J, Broc, D, & Laine, C. "Seismic Analysis of a Nuclear Reactor With Fluid-Structure Interaction." Proceedings of the ASME 2005 Pressure Vessels and Piping Conference. Volume 4: Fluid Structure Interaction. Denver, Colorado, USA. July 17–21, 2005. pp. 37-44. ASME. https://doi.org/10.1115/PVP2005-71182
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