Prof. Yassin A. Hassan

Affiliation: the Royce E. Wisenbaker ‘39 II Chair in Engineering, professor in the Department of Nuclear Engineering and the J. Mike Walker ’66 Department of Mechanical Engineering
Dr. Yassin Hassan Short bio

Dr. Yassin Hassan is the Royce E. Wisenbaker ‘39 II Chair in Engineering, professor in the Department of Nuclear Engineering and the J. Mike Walker ’66 Department of Mechanical Engineering.

He received his master’s and doctorate in nuclear in nuclear engineering from the University of Illinois, and a master’s in mechanical engineering from the University of Virginia. He is a fellow of the American Association for the Advancement of Science, the American Society of Mechanical of Mechanical Engineers and American Nuclear Society (ANS). He was awarded the 2017 James N. Landis Medal of the American Society of Mechanical Engineers, 2008 ANS Seaborg award, 2004 Thermal Hydraulics Technical Achievement award, 2003 Arthur Holly Compton Award of the American Nuclear Society, 2003George Westinghouse Gold Medal award and the 2001 Glenn Murphy Award of the American Association for Engineering Education. In 2007, Hassan was sworn in as a part-time technical judge to the Atomic Safety and Licensing Board Panel of the U.S. Nuclear Regulatory Commission.

He has authored more than 490 refereed publications in technical journals and conference proceedings (195 technical journals and 295 conferences) and more than 380 summaries in American Nuclear Society transactions (the largest for any ANS member since its establishment in 1950). He also serves as editor-in-chief of the Journal of Nuclear Engineering and Design and is associate editor of the Journal of Verification, Validation and Uncertainty Quantification.  He is elected to National Academy of Engineering in 2019.

Presentation Title: High Fidelity Experimental Data for Computational Fluid Dynamics Validation in Nuclear Applications

Abstract of presentation:

Significant advances have been made in developing computational fluid dynamics tools to simulate the complex flows in nuclear reactor components; however, there remains a need for obtaining high-fidelity experimental data for validation of these computational codes. The transparent linkage between the experiment and the computer program would allow systematic error identification and uncertainty quantification.

Non-invasive methods for flow velocity and temperature measurements have been continuously increasing in popularity and prevalence across many areas of experimental single and multiphase flows and with applications that range across academic research and industrial application. A series of experimental work to achieve high-fidelity measurements of single and multiphase bubbly flows are performed. In this talk several novel experimental techniques aimed at providing experimental databases with high quality, high spatial and temporal resolutions will presented. The talk will cover examples of the results in several practical applications in nuclear reactor applications. The whole-field velocity data are used for validation of computational fluid dynamic computer programs and development of mechanistic models in complex geometries. The use of the experimental data for development of turbulence models such as Reynolds-Average Navier Stokes (RANS), hybrid techniques and Large Eddy simulations (LES) will be discussed.