Assistant Professor of Nuclear Science and Engineering
PhD, Nuclear Engineering, Tokyo Institute of Technology, 2004.
M.S., Nuclear Engineering, University of Pisa, 2002.
The availability of more robust and physically realistic turbulence models will bring immediate and major improvements to the reactor's economic and safety performance. The unique generality of the approaches that we are developing allows designing new configurations and innovative concepts, accurately reproducing complex flow and heat transfer distributions; these improvements directly translate into higher efficiency and reduced failures.
Unsteady flow phenomena
Unsteady flows are often encountered in nuclear applications and can strongly affect the efficiency and reliability of components. Understanding of the underlying physical mechanism and development of groundbreaking modeling techniques is a focus of our research.
Multiphase flow and boiling
Computational multi-phase flow techniques are being developed to provide a faithful representation of the complex boiling and two-phase flow regimes. Applications include the use of interface tracking techniques to develop cross-flow correlations for subchannel analysis codes and use of the Euler-Euler approach to represent the boiling phenomena in PWR and BWR cores. These methods have demonstrated great potential, and pioneering work is ongoing to bring them up to develop reliable design tools.
Virtual Reactor Modeling
Development of innovative computational approaches is being incorporated with the ability of implementing full scale detailed models of reactor designs. These high quality, large scale models will incorporate validated multiphysics in order to predict complex multileveled interactions in the early stage of the design. Such innovative tool will significantly modify the project approach for advanced solutions and innovative concepts.
- A. Shams, F. Roelofs, E.M.J. Komen, E. Baglietto, 2012. Optimization of a pebble bed configuration for quasi-direct numerical simulation, Nuclear Engineering and Design, Volume 242, January 2012, Pages 331-340.
- E. Baglietto, 2011. An Algebraic Heat Flux Model in STAR-CCM+ for Application to Innovative Reactors, Proceedings of the NURETH14 Conference, Toronto, Ontario, Canada.
- Jin Yan, Brendan Kochunas, Mathieu Hursin, Thomas Downar, Zeses Karoutas, Emilio Baglietto, 2011. Coupled Computational Fluid Dynamics and MOC Neutronic Simulations of Westinghouse PWR Fuel Assemblies with Grid Spacers, Proceedings of the NURETH14 Conference, Toronto, Ontario, Canada.
- A. M. Elmahdi, R. Lu, M. E. Conner, Z. Karoutas, E. Baglietto, 2011. Flow Induced Vibration Forces on a Fuel Rod by LES CFD Analysis, Proceedings of the NURETH14 Conference, Toronto, Ontario, Canada.
- S.T. Jayaraju, E.M.J. Komen, E. Baglietto, 2010. Suitability of wall-functions in Large Eddy Simulation for thermal fatigue in a T-junction, Nuclear Engineering and Design, Volume 240 (2010) 2544-2554.
- Z. Karoutas, K. Lang, P. Joffre, E. Baglietto, R. Brewster, E. Volpenhein, 2010. Evaluating PWR Fuel Performance Using Vessel CFD Analysis, Proceedings of 2010 LWR Fuel Performance, Orlando, Florida, USA.
- J. Fort, J. Cuta, C. Bajwa, E. Baglietto, 2010. Modeling Heat Transfer in Spent Fuel Transfer Cask Neutron Shields—A Challenging Problem in Natural Convection, Proceedings of the ASME Conference PVP2010, Bellevue, Washington, USA.
- E. Merzari, H. Ninokata, S. Wang, E. Baglietto 2009. Numerical simulation of free-surface vortices, Nuclear Technology, Vol. 165 (2009).
22.313J Thermal Hydraulics in Power Technology
22.315 Applied Computational Fluid Dynamics and Heat Transfer
- 2005 Best Paper Award from the Thermal-Hydraulics Division of the American Nuclear Society, Washington D.C, November 2005.
- Invited Lecturer to the 2005 Dr Forum of the Atomic Energy Society of Japan, September 15th and 16th 2005, Hachinoue, JAPAN.