In the framework of the studies on the seismic behaviour of the PWR reactor cores, models have been built to describe the dynamic behaviour of one fuel assembly, one assembly row or of the whole core. Behaviour models currently restrain the study to the central row of the core. These “One Row Models” (2D vertical models) use beam models for the assemblies and do not consider interactions between the assemblies by the fluid. Recent models consider the whole core (2D horizontal models), with the objective to describe the interactions between the different rows by the fluid. This paper presents a new step to build a complete 3D whole core model, with calculations of vertical fluid flow that can take place in a 2D “one row model”. These vertical flows leads to interactions between the assemblies, even if only one row is considered.
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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
Daniel Broc
Daniel Broc
CEA Saclay, Gif-sur-Yvette, France
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Daniel Broc
CEA Saclay, Gif-sur-Yvette, France
Paper No:
PVP2005-71189, pp. 83-88; 6 pages
Published Online:
July 29, 2008
Citation
Broc, D. "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. 83-88. ASME. https://doi.org/10.1115/PVP2005-71189
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