TRACK CHAIR

Suyuan YU 

Education
1994.9--1998.9 Ph.D. Department of Mechanical Engineering
University of California Davis
1983.9--1989.12  BS MS  Department of Engineering Mechanics
Tsinghua University

Work Experience
2013.10-now     Professor, Center for Combustion Energy
Tsinghua University
1999.12-2013.10 Professor and Associate Professor
INET, Tsinghua University
1998.10-1999.9  Postdoctoral Research Scientist
Department of Chemical Engineering
Yale University
1989.12-1994.9  Lecturer,  INET Tsinghua University

Academic Positions
Editorial Board Members for《PARTICUOLOGY》,《Nuclear Power Engineering》and《International Journal of Nuclear Energy Science and Technology》

Advisory Board Member for International Association of Structural Mechanics in Reactor Technology
Board Member of Chinese Particle Association
Director of Chinese Association of Magnetic Bearings Technology
Board Member of International Association of Magnetic Bearing
Expert Member of National Association of Vibration and Noise Control

Research Interests
Combustion, Particology, Graphite, Active Magnetic Bearing

Research Fields
Combustion: Chemical kinetics and pollutant production in an incineration, Combustion theory and application, Microgravity Combustion
Particology:  Physical and chemical mechanism of aerosol and haze nucleation and development, Theory and experiment on dust resuspension, Dust detonation mechanism；
Graphite：Graphite oxidation and its irradiation effects；
Magnetic Bearing: Principle, design, technology and application of Active Magnetic Bearings, Active control of vibration and noise for rotational machinery.

Research Highlights
National Natural Science Foundation of China projects: “Quantum chemical study on Chromium incineration”, “Chemical kinetics and quantum chemical model of hazardous chromium waste”, “The kinetic study on deposition of hazardous chromium waste”, and NNSFC key project “The technologies of HTGR and helium gas turbine”.
Be in charge of the National Key Project “Research on active magnetic bearing for principle helium blower” and “The releasing behavior of graphite dust at incident conditions”, and dozens of other projects in particle dynamics, deposition and resuspension, active magnetic bearing，and vibration and noise control.

Honours and awards
ICONE Award，2015
“Outstanding Talent for New Century” by Ministry of Education of China
“Excellent Professor” by Beijing Municipal
“Excellent Young Faculty” by Ministry of Education of China
“Academic Young Talent” by Tsinghua University

Publications
4 books, over 50 SCI papers and around 150 EI papers have been published nowdays.

Igor Pioro

Professor Igor Pioro – Ph.D. (1983), Doctor of Technical Sciences (1992), Professional Engineer (Ontario, Canada) (2008), Fellow of the American Society of Mechanical Engineers (2012), Canadian Society of Mechanical Engineers (2015) and Engineering Institute of Canada (EIC) (2013) is an internationally recognized scientist within areas of nuclear engineering (thermalhydraulics of nuclear reactors, Generation-IV nuclear-reactor concepts, etc.) and thermal sciences / engineering (boiling, forced convection including supercritical pressures, etc.).  He is author/co-author of more than 425 publications including 9 technical books, 15 chapters, 89 papers in refereed journals, 242 papers in refereed proceedings of international and national conferences, 26 patents and inventions, and 46 major technical reports.
Dr. Pioro graduated from the National Technical University of Ukraine "Kiev Polytechnic Institute" with Master of Applied Science in Thermal Physics in 1979.  After that, he worked on various positions including an engineer, senior scientist, deputy director, professor, director of the graduate program in nuclear engineering, and associate dean.  Currently, he is associated with the Faculty of Energy Systems and Nuclear Science University of Ontario Institute of Technology (Oshawa, Ontario, Canada).
Dr. Pioro is a Founding Editor of the ASME Journal of Nuclear Engineering and Radiation Science.  He was a Chair of the Executive Committee of the Nuclear Engineering Division of the ASME (2011-2012) and a Chair of the International Conference On Nuclear Engineering (ICONE-20) (2011-2012).
Professor Pioro has received many international and national awards and certificates of appreciation including an Honorary Doctor’s Degree from the National Technical University of Ukraine “Kiev Polytechnic Institute” (2013); The Canadian Nuclear Society (CNS) Education and Communication Award (2011); The UOIT Research Excellence Award (2011); the ICONE Award from the American Society of Mechanical Engineers (ASME) (2009); etc.
 

PAN Liangming

Education: Chongqing University, Chongqing, Ph.D. in Engineering Thermophysics, 2002, School of Power Engineering, Advisor: Professor Ming-dao Xin.

Ph.D Thesis: Bubble Behavior and Heat Transfer of Subcooled Boiling in Vertical Narrow Rectangular Channel, Area of research: Engineering Thermophysics, Advisor: professor Ming-dao Xin, Year of Publication:2002

Experiences:
9/2007 – present: Professor, School of Power Engineering, Chongqing University, Taught course on Engineering Fluid Mechanics, Advanced Fluid Mechanics, Nuclear Reactor Thermal hydraulic Analysis, Boiling Heat Transfer and Two-phase Flow.
1/2006 – present: Associate Dean, School of Power Engineering, Chongqing University, in charge of researching affair and international affair of the school.
7/2013 – 2/2014: Visiting Scholar, School of Nuclear Engineering, Purdue University. Worked on experimental investigation about flow pattern in 1-inch tube.

Research Areas:
(1) Engineering Thermophysics: Two-phase flow and heat transfer, bubble dynamics.
(2) Numerical simulation and CFD application: Bubble dynamics numerical simulation.

Specific Work Expertise/Skills:
(1) Fluent CFD software simulation;
(2) Bubble dynamics experimental investigation.

Patents:
(1) Method and system for zero emission treatment of desulfured waste water, CN102180549A, 2011.03.29
(2) Method and system for removing inhalable particles, CN102626577A, 2012.04.09

Sama Bilbao y León

Sama Bilbao y León joined the Department of Mechanical and Nuclear Engineering at Virginia Commonwealth University (VCU) in January 2011 as Director of Nuclear Engineering Programs and Associate Professor. She is one of the key individuals involved in the creation and development of the thriving new Nuclear Engineering program at VCU. Until December 2010, Sama was the Technical Head of the International Atomic Energy Agency (IAEA) Water Cooled Reactors Technology Development Unit and she was in charge of all IAEA activities in support of the development and near term deployment of advanced water cooled reactors and their associated fuels. From February 2001 until March 2008, Sama was a Nuclear Safety Analysis Engineer at Dominion Generation, where she worked on the development and licensing of new methodologies in core thermal-hydraulics and nuclear safety analysis in support of Dominion’s nuclear power stations.  Previously, as a researcher at the University of Wisconsin – Madison, Sama conducted research on experimental and computational thermal-hydraulics and nuclear safety, energy and environmental policy, as well as public perception. She also participated in the design of nuclear micro-batteries to power nano-devices. At the Escuela Técnica Superior de Ingenieros Industriales of the Universidad Politécnica in Madrid she was involved in the simulation and analysis of severe accidents and nuclear safety. In November 2013 Sama was appointed by Virginia Governor McDonnell and VCU President Rao to the Virginia Nuclear Energy Authority Board, and elected Treasurer. In January 2014 Sama was appointed to the Institute of Nuclear Power Operations (INPO) National Accreditation Board. In January 2015 Sama was elected Vice-Chair of the Board of the Virginia Nuclear Energy Consortium.
Sama is one of the seven founders of the North American Young Generation in Nuclear (NA YGN), and served as Public Information Chair since its creation in 1999 until May 2005. Sama is also an active member of the American Nuclear Society (ANS) since 1995, both nationally and locally (currently VCU student section and Virginia local section). Her dedication to spreading the good news about nuclear earned her the ANS 2002 Public Communications Award. In 2007 she received the NA-YGN Founder Award, the highest award given to an NA-YGN member, which rewards leadership, vision and dedication. In 2007, and again in 2010, Sama was elected to the national Board of Directors of the American Nuclear Society. In 2011, she received the ANS Mary Jane Oestmann Women’s Achievement Award. In 2014 she received an ANS Presidential Citation for her continuous dedication to ANS. Sama is also a member of ASME, ASEE, SWE and WIN.
Sama holds a bachelor’s degree in Mechanical Engineering and a master’s degree in Energy Technologies from the Polytechnic University of Madrid; a master's degree and a PhD in Nuclear Engineering and Engineering Physics from the University of Wisconsin – Madison; and an MBA from Averett University.
 

Tomio Okawa

Tomio Okawa is a professor of Department of Mechanical Engineering & Intelligent Systems, Graduate School of Informatics & Engineering, The University of Electro-Communications, Tokyo, Japan. He was graduated from Department of Applied Physics, Faculty of Science, Tokyo Institute of Technology in 1988, completed Master's program of Department of Nuclear Engineering, Division of Science and Engineering, Graduate School of Tokyo Institute of Technology in 1990, and got the degree of Dr. Eng. in 1995. He worked for Central Research Institute of Electric Power Industry (CRIEPI) and Osaka University for 20 years, and then move to the present position in 2011. His current research areas are thermal-hydraulics and nuclear engineering.

Hyoung Kyu Cho

Education
Seoul National University (Seoul, Korea)
Department of Nuclear Engineering
 Ph.D. in Nuclear Engineering (August 2004)/ Nuclear Thermal Hydraulics
 Master in Nuclear Engineering (February 2000) /Nuclear Thermal Hydraulics
 B.A. in Nuclear Engineering (February 1998)

Dissertation
 “Scaling Analysis for the Multidimensional Phenomena of the ECC Bypass during a LBLOCA with the Direct Vessel Injection”, Ph.D. Degree August 2004
 “An experimental study for the hydraulic phenomena in the KNGR downcomer during a LBLOCA reflood phase”, Master Degree February 2000

Academic experiences
 Assistant professor, Department of Nuclear Engineering, Seoul National University, Mar. 2013 – present
 Senior Researcher, Thermal-Hydraulic Safety Research Division, Korea Atomic Energy Research Institute, Jan. 2005 – Feb. 2013
 Visiting Researcher, Service de Simulation en Thermohydraulique, CEA-Grenoble, Oct. 2010 – Jun. 2011
 Post doctor, Department of Nuclear Engineering, Seoul Nation University, Aug. 2004- Dec. 2004

Selected research projects
 High-resolution simulation and validation for thermal-hydraulic phenomena in nuclear reactor components, Source of support: Nuclear Safety and Security Commission
- Film condensation modelling for component and CFD scale codes
- Multi-scale simulation of passive cooling systems with coupled system-component analysis code
- Investigation of bubble behaviors on a horizontal heat exchanger
 Design Code Licensing and Establishment of Application System for NPP, Source of support: Ministry of trade, industry and energy
- Validation of the multi-dimensional modules in nuclear reactor system analysis codes
 Development of Numerical Simulation Technology for High-Resolution Thermal Hydraulic Analysis, Source of support: Ministry of Science, ICT and Future Planning (~2011)

- Development of component scale T/H analysis code
- Heat structure coupling of system scale and component scale codes
- Two-phase flow model implementation
- Code development and verification
 Experimental Study on the Convective Phenomena in the Riser for Developing the Scaling Analysis Method of the Reactor Cavity Cooling System, Source of support: Korea Atomic Energy Research Institute (International Nuclear Energy Research Initiative)
- Experiment on convective heat transfer in the riser of VHTR reactor cavity cooling system
- Verification of the scaling analysis for the reactor cavity cooling system
 Development of VHTR Thermo-Fluid Design Verification Technology, Source of support: Ministry of Science, ICT and Future Planning
- Development of a flow network analysis code for the bypass and cross flow prediction in a VHTR core
- Experiment on the cross flow in a VHTR core