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Seminar: Coupling of CFD with 1D TH and the Use of CFD-grade Experiments for Code Validation

Professor Annalisa Manera will be presenting as part of the nuclear engineering seminar series.

All dates for this event occur in the past.

E141 Scott Lab
201 W. 19th Ave.
Columbus, OH 43210
United States

Speaker: Professor Annalisa Manera, Department of Nuclear Engineering, University of Michigan

Abstract:

Results obtained on the coupling between the U.S. Nuclear Regulatory Commission (NRC) best estimate-thermal hydraulic code TRACE and the computational fluid dynamics (CFD) code ANSYS-CFX will be presented, with special emphasis on the challenges encountered with 1D/3D interfaces and appropriate code validation. The talk will also address the design and performance of CFD-grade experiments aimed at the validation of advanced computational methodologies in thermal hydraulics.

Bio:

Dr. Annalisa Manera, after received a Ph.D. in Nuclear Engineering from the Delft University of Technology (The Netherlands), worked as scientist at the Research Center Rossendorf-Dresden (Germany), before becoming the Head of the group of “Nuclear systems behaviour” in the Laboratory of Reactor Physics at the Paul Scherrer Institute (Switzerland).  With her group providing technical support to the Swiss Nuclear Authority, her research was focused on state-of-the-art methodologies for nuclear plants safety analyses, including coupling between TH and 3D neutron kinetics, and computational fluid dynamics.  Since June 2011 Annalisa Manera is associate professor in the Nuclear Engineering Department at the University of Michigan.  Her research interests include experimental thermal-hydraulics, computational fluid dynamics, and multi-physics methods for power reactor safety analysis.