Michael Z. Podowski

Mechanical, Aerospace and Nuclear Engineering

About

Professor Podowski is an internationally-recognized expert in multiphase flow and heat transfer technology, and in nuclear reactor engineering.  He was Director of the Center for Multiphase Research (CMR) and Chairman of the Department of Nuclear Engineering and Engineering Physics at Rensselaer Polytechnic Institute. He has served as technical expert and consultant to numerous institutions worldwide. Gave a total of nearly 140 plenary and keynote lectures, seminars and other invited talks. Authored or co-authored over 360 peer-reviewed publications and books/book-chapters, including 70+ archival papers in the following journals: 

Int. J. of Multiphase Flow, J. of Heat Transfer, Physics of Fluids, J. of Fluids Engineering, J. of Multiphase Flow and Heat Transfer, IEEE Transactions on Automatic Control, Int. J. - Heat and Technology, Int. J. of Heat and Mass Transfer, Int. J. - Chemical Engineering Communications, Archives of Thermodynamics, Advances in Colloid and Interface Science, Nanotechnology, Physico-Chemical Hydrodynamics, J. of Power and Energy Sys­tems, Theoretical and Computational Fluid Dynamics, Int. J. of Numerical Meth­ods for Heat and Fluid Flow, Computers & Fluids, Nucl. Sci. and Eng., Nucl. Technology, Nucl. Eng. and Des., Nucl. Eng. and Technology, Atomk­ernenergie, Annals of Nuclear Energy, Science and Technology of Nuclear Installations.

Education & Training

M.S., Mechanical Engineering, Warsaw University of Technology, Poland, 1965

M.S., Mathematics, University of Warsaw, Poland, 1970

Ph.D., Nuclear Engineering, Warsaw University of Technology, 1972

D.Sc. (Habilitation), Nuclear Engineering, Warsaw University of Technology, 1975

Research

Primary Research Focus
Multiphase Flow and Heat Transfer
Other Focus Areas

• Fluid Flow and Heat Transfer in Supercritical Fluid Systems
• Computational Fluid Dynamics
• System Stability
• Nuclear Reactor Thermal Hydraulics
• Nuclear Reactor Dynamics and Control
• Nuclear Reactor Safety

Publications

The following is a selection of recent publications in Scopus. Michael Z. Podowski has 140 indexed publications in the subjects of Engineering, Energy, Physics and Astronomy.

On the importance of consistency of multiple-level modeling of multiphase flow in reactor systems
Michael Z. Podowski
Nuclear Engineering and Design
, 409
, 2023
.
Impact of consistency between modeling detail and physical uncertainties on severe accident predictions
Michael Z. Podowski, Raf M. Podowski, Dong Ha Kim, Jun Ho Bae, Dong Gun Son
Nuclear Engineering and Design
, 384
, 2021
.
Advancements in reactor stability analysis methods; personal perspective
Michael Z. Podowski
Nuclear Engineering and Design
, 376
, 2021
.
Computational and experimental analysis of gas/liquid two-phase flow in rod bundles with mixing-vane spacer grids
Brian M. Waite, Horst Michael Prasser, Michael Z. Podowski
Nuclear Engineering and Design
, 360
, 2020
.
Understanding two-phase flow and boiling heat transfer: Challenges and paradoxes
Michael Z. Podowski
Nuclear Engineering and Design
, 354
, 2019
.
The life and the contribution of B. R. Sehgal, G. Yadigaroglu and G. Hewitt: Remembrance statements
N. Aksan, M. Andreani, S. Bechta, M. Corradini, F. D'Auria, V. Dhir, W. Frid, J. Jones, Kim Jong, J. Lillington, O. Matar, Nam Dinh, H. Ninokata, M. Podowski, S. Revankar, J. Riznic, N. Todreas, H. Tuomisto, E. Uspuras, S. Walker, J. Zhang
Nuclear Engineering and Design
, 354
, 2019
.
COMPASS - New modeling and simulation approach to PWR in-vessel accident progression
Michael Z. Podowski, Raf M. Podowski, Dong Ha Kim, Jun Ho Bae, Dong Gun Son
Nuclear Engineering and Technology
, 51
, 2019
, pp.1916-1938
.
Is reactor multiphase thermal-hydraulics a mature field of engineering science?
Michael Z. Podowski
Nuclear Engineering and Design
, 345
, 2019
, pp.196-208
.
Analytical modeling of the effect of heater geometry on boiling heat transfer
Zeyong Wang, Michael Z. Podowski
Nuclear Engineering and Design
, 344
, 2019
, pp.122-130
.
Formulation and validation of a three-dimensional computational model of simultaneous interfacial evaporation and condensation in subcooled boiling
Hong Jiao, Michael Z. Podowski
International Journal of Multiphase Flow
, 112
, 2019
, pp.130-154
.

News

ADDITIONAL PUBLICATIONS

Selected Journal Papers 

  • M.Z. Podowski, S. Kasprzak, 2024. Nuclear reactor safety analyses; Transfer of experience gained in Poland to the USA, Sweden and South Korea. Advances in Nucl. Techn., V.67, 2-28.
  • H.Jiao, M.Z. Podowski, 2019. Three-dimensional model of evaporation/ condensation at bubble/liquid interface in subcooled boiling.  Int. J. Multiphase Flow, 112, 130-154.
  • J.H. Bae, D. Son, J. Kim, R-J. Park, J-H. Park, D. H. Kim, J-H. Song, M. Z. Podowski, 2017. Core degradation simulation of the PHEBUS FPT3 experiment using COMPASS code.  Nucl. Eng. Des., 320, 258-268.
  • F. Behafarid, M.Z. Podowski, 2016. Modeling and computer simulation of centrifugal CO2 compressors at supercritical pressures. J. Fluids Eng., V.138, 1-9.
  • F. Behafarid, K.E. Jansen, M.Z. Podowski, 2015. Theoretical and computational study on large bubble motion and liquid film in inclined and vertical narrow conduits.  Int J. Multiphase Flow, V.75, 288-299.
  • J. Zhong, S.P. Antal, M.Z. Podowski, Impact of local property variations of reactor coolant on cladding temperature distribution in supercritical water reactors, 2014.  Journal of Power Technologies, V.94, 49-58.
  • F. Behafarid, D. Shaver, S.P. I.A. Bolotnov, S.P. Antal. K.E. Jansen, M.Z. Podowski, 2013. Coupled DNS/RANS Simulation of fission gas discharge during loss-of-flow accident in Gen-IV sodium fast reactor. Nuclear Technology, V.181, No.1, 44-55.
  • M.Z. Podowski, 2012. Toward mechanistic modeling of boiling heat transfer. Nucl. Eng.  Techn., V.4, No.8, 1-8.
  • I.A. Bolotnov, S.P. Antal, K.E. Jansen, M.Z. Podowski, 2012. Multidimensional analysis of fission gas discharge following fuel element failure in sodium fast reactor.  Nucl. Eng. Des., 247, 136-146.
  • I.A. Bolotnov, K.E. Jansen, D.A. Drew. A.A. Oberai, R.T. Lahey, Jr., M.Z. Podowski, 2011. Detached direct numerical simulations of turbulent two-phase bubble channel flow. Int J. Multiphase Flow, 37, 647-659.
  • W.R. Schlichting, R.T. Lahey, Jr., M.Z. Podowski, 2010. An analysis of interacting instability modes in a phase change system. Nucl. Eng. Des., 240, 3178-3201.
  • E.A. Tselishcheva, S.P. Antal, M.Z. Podowski, 2010. Mechanistic multidimensional analysis of horizontal two-phase flows. Nucl. Eng. Des., 240, 405-415.
  • P. Tiwari, S.P. Antal, M.Z. Podowski, 2009. Modeling shear-induced diffusion force in par­ticulate flows. Computers & Fluids, 38, 727–737.
  • M.Z. Podowski, 2009. On the consistency of mechanistic multidimensional modeling of gas/ liquid two-phase flows. Nucl. Eng. Des., 239, 933–940.
  • M.Z. Podowski, R.M. Podowski, 2009. Mechanistic multidimensional modeling of forced-convection boiling heat transfer. Sci. & Techn. Nucl. Inst., V. 2009, Article ID 387020.
  • T. Gallaway, S.P. Antal, M.Z. Podowski, 2008. multidimensional model of fluid flow and heat transfer in generation-IV supercritical water reactors. Nucl. Eng. Des., 238, 1909–1916.
  • M.Z. Podowski, 2008. Multidimensional modeling of two-phase flow and heat transfer. Int. J. Num. Meth. Heat & Fluid Flow, V. 18, Issue ¾, 491-513.
  • M.Z. Podowski, 2008. Thermal hydraulic aspects of SCWR design. J. Power & En­ergy. Sys., 2, 1, 352-360.
  • B. Wierzbicki, S.P. Antal, M.Z. Podowski, 2007. On the modeling of gas bubble evolution and transport using coupled Level-Set/CFD method. Nucl. Techn., 158, 2, 261-274.
  • P. Tiwari, S.P. Antal, M.Z. Podowski, 2006. Three-dimensional fluid mechanics of particu­late two-phase flows in U-bend and helical conduits. Physics of Fluids, 18, 4, 1-18.
  • S. Vafaei, T. Borca-Tasciuc, M.Z. Podowski, A. Purcayastha, G. Ramanah, P.M. Ayajan, 2006. Effect of nanoparticles on sessile droplet contact angle. Nanotechnology, 17, 2523-2527.
  • M.Z. Podowski, 2005. Understanding multiphase flow and heat transfer: perception, reality, future needs", Archives of Thermodynamics, 26, 3,.1-18.
  • S. Vafaei and M.Z. Podowski, 2005. Analysis of the relationship between liquid droplet size and contact angle. Advances in Colloid and Interface Science, 113, 133-146.
  • S. Vafaei and M.Z. Podowski, 2005. Theoretical model of contact angle and shape of droplets on solid substrates. Nucl. Eng. Des., 235, 1293-1301.
  • P. Tiwari, S.P. Antal, G. Belfort, A. Burgoyne, M.Z. Podowski, 2004. Multifield computation­al fluid dynamics model of particulate flow in curved circular tubes. Theoret. Comp. Fluid Dynamics, 18, 205-220.
  • M.Z. Podowski, A. Kumbaro, 2004. The modeling of thin liquid films along inclined sur­faces. J. Fluids Eng., 126, 565-572. 
  • J.L. Munos-Kobo, M.Z. Podowski, S. Chiva, 2002. Parallel channel instabilities in boiling water reactor systems: boundary conditions for out-of-phase oscillations. Annals of Nu­clear Energy, 29, 1891-1917.
  • H. Anglart, M.Z. Podowski, 2002. Fluid mechanics of Taylor bubbles and slug flows in ver­tical channels", Nucl. Sci. Eng, V.140, No.2, 165-173.
  • J. Zhou, M.Z. Podowski, 2001. Modeling and analysis of hydrodynamic instabilities in two-phase flow using two-fluid model, Nucl. Eng. Des, 204, 129-142.

Selected Book Chapters

  • J. Yin, R.T. Lahey, Jr., M.K Jensen, M.Z. Podowski, 2006. An analysis of interacting instability modes. In Multiphase Science and Technology, Vol. 18, Hemisphere Publishing Corporation (J.M. Delhaye, G.F. Hewitt and N. Zuber - Editors), Hemisphere Publishing Corp.
  • P. Tiwari, S.P. Antal, M.Z Podowski, 2003. On the modeling of dispersed particulate flows using a multifield model. In Computational Solids and Fluids Mechanics (ed. K.J. Bathe), Elsevier Sci­ence LTD. 
  • A. Alajbe­govic, N. Kurul, M.Z. Podowski, D. Drew, R.T. Lahey, Jr., 2000. Mechanistic modeling of CHF in forced-convection subcooled boiling. In Convective and Pool Boiling (F. Mayinger - Editor), Begell House, New York.
  • M.Z. Podowski, 1992. Two-phase flow dynamics. In Boiling Heat Transfer (R.T. Lahey, Jr. - Editor), Elsevier Publishing Corp.
  • M.Z. Podowski, 1992. Instabilities in two-phase systems. In Boiling Heat Transfer (R.T. Lahey, Jr. - Editor), Elsevier Publishing Corp.

SELECTED PLENARY, KEYNOTE AND INVITED LECTURES

  • “In Search of Efficient Methods to Capture Dominant Multiphase Flow and Heat Transfer Phenomena”, Int. Topical Meeting on Reactor Thermal Hydraulics (NURETH-20), Washington, DC, Aug. 21, 2023.
  • “Recent Developments in the Modeling of Forced-Convection Subcooled Boiling”, Int. Conf. om Multiphase Flow, Gdansk, Poland, June 14, 2023.
  • “Multiple-Level Modeling of Multiphase Flows”, Int. Conf. om Multiphase Flow, Gdansk, Poland, June 13, 2023.
  • “Personal Remarks on Our Understanding of Multiphase Flow and Heat Transfer, with the Emphasis on Nuclear Reactor Applications”, Int. Topical Meeting on Reactor Thermal Hydraulics (NURETH-19), Brussels, Belgium, March 9, 2022, 2023.
  • "On the Importance of Multiple-Scale Phenomena in Mechanistic Modeling or Reactor Thermal-Hydraulics", OECD/NEA/CSNI Specialists Meeting, Madrid, Spain, Dec., 2021.
  • "Impact of Consistency between Modeling Detail and Physical Uncertainties on Severe Accident Predictions", OECD/NEA/CSNI Specialists Meeting, Madrid, Spain, Dec., 2021.
  • "Understanding Two-Phase Flow and Boiling Heat Transfer: Challenges and Paradoxes”, Int. Topical Meeting on Reactor Thermal Hydraulics (NURETH-18), Portland, OR, Aug., 2019.
  •  “On the Mechanistic Modeling of Fluid Flow and Heat Transfer in Supercrit­ical Pressure Systems”, 6th Int. Conference on Mechanical & Aerospace Engineering, Atlanta, GA, Nov., 2018.
  • “Overview of Fundamentals and Applications of Multiphase/Multi­component Flow and Heat Transfer, Department of Mechanical Engineering, Texas Tech Uni­versity, Lubbock, TX, Oct. 22, 2018.
  • “Is Multiphase Flow and Heat Transfer a Mature Field of Science?”, Interna­tional Conference & Workshop REMOO, Venice, Italy, May 29, 2018.
  • “On the Use of Multiscale Approach and High-Fidelity Data in the Develop­ment of Multiphase CFD Models and Mechanistic Closure Laws", Workshop on High-Resolu­tion Single- and Two-Phase Flow Analysis and Model Development, Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi’an, China, Sep. 3, 2017. 
  • "Is Reactor Multiphase Thermal Hydraulics a Mature Field of Engineering Science?", Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi’an, China, Sep. 4, 2017.
  • "Perspective on Nuclear Power: Current Status and Future Trends", National Research Nuclear University, American University in Moscow, Russia, May 2, 2017.
  • “Remarks on Ways to Improve our Understanding of Severe Accident Pro­gression”, Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11), Oct., 2016.
  • “On the Modeling and Computer Simulation of Multiphase Flow and Heat Transfer in Reactor Systems” GE-Hitachi, Wilmington, NC, March 16, 2016.
  •  “Toward Mechanistic Modeling of Two-Phase Flow and Heat Trans­fer in Reactor Fuel Assemblies”, Department of Nuclear Engineering, North Carolina State University, Raleigh, NC, March 14, 2016.
  • “Core Meltdown Accidents; Lessons Learned from Fukushima”, 3rd Japan-U.S. Forum on Fukushima Recovery and Decommissioning, Tokyo, Japan, Feb. 23, 2016.
  • “Accident Modeling Challenges and The Lessons Learned From Fukushima”, 2015 International Workshop on Post-Fukushima Challenges on Severe Accident Mitigation and Research Collaboration, Daejeon Korea, Nov. 10, 2015.
  • “Multidimensional Modeling Capabilities of Two-Phase Flow and Heat Transfer in Reactor Fuel Assemblies; Current Status and Future Needs”, International Seminar on Sub-Channel Analysis, CFD and CHF (ISACC-2015), Shenzhen, China, Dec. 6, 2015.
  • “On the Modeling of Two-Phase Flow and Heat Transfer In Reactor Fuel Assemblies”, KEPCO Nuclear Fuel, Daejeon, Korea, Nov. 11, 2015.
  • "Remarks on Selected Multiscale Modeling Issues in Multiphase Flow and Heat Transfer", INTERPACK/ICNMMS Conf., San Francisco, CA, July 7, 2015.
  • "Modeling and Computer Simulation of Multiphase Flow and Heat Transfer in Reactor Systems", National Center for Nuclear Research, Swierk, Poland, June 23, 2015.
  • "Recent Advancements in the Modeling and Computations of Two-Phase Flow and Boiling Heat Transfer", Int. Workshop on Multiphase Flow", Institute of Turboma­chinery, Gdansk, Poland, June 19, 2015.
  • "Nanoscale-to-Macroscale Multiphase Systems: Issues and Challenges", Int. Conference on Multiphase Systems: Nature, Man, Society, Technologies, Part-II, Russian Academy of Sciences, Moscow, Russia, July 17, 2015.
  • "Nuclear Power Reactor Safety: Perception vs. Reality, Impact of Progress in Multiphase Science", Int. Conference on Multiphase Systems: Nature, Man, Society, Technol­ogies, Part-I, on board of ’Akademik Ioffe’ - research ship of the Russian Institute of Oceanol­ogy, Baltic Sea, July 8, 2015.
  • "Remarks on Nuclear Power Reactor Safety", National Research Nuclear Uni­versity, American University in Moscow, May 20, 2015.
  • “Toward Development of Mechanistic Models of Two-Phase Flow and Boiling Heat Transfer”, 31st Siberian Thermophysical Seminar, Novosibirsk, Russia, Nov. 18, 2014.
  • "Nuclear Power Generation; Current and Future Challenges", KINGS, South Korea, Oct. 8, 2014.
  • "Model Verification and Validation Issues for Multiphase Flow and Heat Transfer Simulation in Reactor Systems", CFD4NRS-5, OECD/NEA & IAEA Workshop, Zu­rich, Switzerland, Sepp. 9-11, 2014.
  • "Recent Advancements in Multidimensional Modeling of Two-Phase Flow and Heat Transfer", EUROTHERM Seminar: Transport Phenomena in Multiphase Systems, Krakow, Poland, June 29-July 3, 2014.
  • "Recent Advancements in Mechanistic Multidimensional Modeling of Fluid Flow and Heat Transfer in Fluids at Supercritical Pressures", Int. Meeting of Specialists on Heat Transfer to Fluids at Supercritical Pressure with Application to Nuclear Reactors and So­lar Energy Systems, Manchester, UK, June 30 -July 1, 2014.
  • "Development of Advanced Reactors", meeting on Energy Security of Central Europe, Washington, DC, Oct. 4, 2013.
  • "Recent Advancements in Multidimensional Modeling of Two-Phase Flow and Heat Transfer In Reactor Fuel Assemblies", International Seminar on Subchannel Analy­sis, CFD Modeling and Verification, CHF Experiments and Benchmarking, Xi’an, China, Au­g. 2-4, 2013.
  • “Importance of Coupling between Modeling and Computational Issues in Multiphase Flow and Heat Transfer Simulations”, Two-Phase Flow Workshop, North Carolina State University, May 2, 2013. 
  • “Toward the Development of a Virtual Reactor: Modeling and Com­putational Issues in Multiphase Flow and Heat Transfer”, Department of Nuclear Engineering, University of Michigan, Ann Arbor, MI, Dec. 7, 2012.
  • “Validation of Computational Modeling of Multiphase Flow and Heat Trans­fer”, International Computational Modeling Validation Conference, Sydney, Australia, Jan. 15, 2012.
  • “Challenges in Computational Modeling of Multiphase Flow and Heat Transfer”, International Computational Modeling Validation Conference, Sydney, Australia, Jan.14, 2012.
  • “Toward Mechanistic Modeling of Boiling Heat Transfer”, 6th International Conference on Transport Phenomena in Multiphase Systems, Ryn, Poland, June 29, 2011.
  • “Anticipated Impact of Accident at Fukushima Daiichi on Reevaluation of Nu­clear Plant Safety Systems, Korea Atomic Energy Research Institute (KAERI), Daejon, Korea, June 15, 2011.
  • “Hydrodynamic Effects of S-CO2 Property Variations in Nuclear Energy Systems”, Supercritical CO2 Power Cycle Symposium, Boulder, CO, May 25, 2011.
  • "Passive Safety Systems in Current and Next Generation Reac­tors", Panel Discussion: Situation at the Fukushima Daiichi Nuclear Power Plant, George Washington University, Washington, D.C., May 3, 2011.
  • "Toward the Development of a Virtual Reactor: Modeling and Com­putational Issues in Multiphase Flow and Heat Transfer", Texas A&M University, April 20, 2011.
  • "Application of Supercritical CO2 in Nuclear Energy Systems", Workshop on Supercritical Carbon Dioxide and Material Interactions, Brookhaven National Laboratory, Upton, NY, March 21-23, 2011.
  • "Role of Computational Fluid Dynamics in Advanced Nuclear Reactor Design and Safety Analysis: Current Status and Future Needs", Technical Meeting on Application of CFD Codes for the Design of Advanced Water-Cooled Reactors, Vienna, Austria, Dec. 14-16, 2010.
  • "Advancements in Multiscale Computer Simulations of Two-Phase Flow and Heat Transfer in Nuclear Reactors", CEA Cadarache, France, Dec. 12, 2010.
  • “Supercritical Fluids in Nuclear Energy Systems", Czech Nuclear Energy Re­search Institute, Prague, Nov. 18, 2010.
  • "A Mechanistic Approach to the Modeling of Bubble/Bubble Interactions in Gas/Liquid Flows", ANS Winter Meeting, Las Vegas, NV, Nov. 7-11, 2010.
  • “Recent Advancements in Multiscale Computational Modeling of Multiphase Flows in Nuclear Reactors", MIT, Boston, MA, Sep. 20, 2010.
  • "Importance of Technology Transfer in the Development of Nuclear Power Programs", International Engineering Conference, Warsaw, Poland, Sep. 8-10, 2010.
  • "Computational Approach to Multiscale Multiphysics Modeling of Nuclear Reactors", SciDAC Conference, Chattanooga, TN, July 12-15, 2010.
  • "Stability Analysis of Generation IV Supercritical Water Reactors", IAEA Technical Meeting on Heat Transfer, Thermal Hydraulics and System Design for Supercritical Water-Cooled Reactors, Pisa, Italy, July1-5, 2010.
  • "Recent Advances in Multiscale Simulations of Multiphase Flow for Next Generation Reactors", IAEA, Vienna, Austria, May 21, 2010.         
  • "Toward Next Generation Nuclear Reactors; Concepts, Challenges, Technical Advancements", Joint Meeting of NY and NE Sections of American Physical Society, Schenectady, NY, April 24, 2010.
  • "Multiscale Modeling of Multiphase Flow in Gen. IV Reactors", Pur­due University, West Lafayette, IN, April 21, 2010.
  • "Recent Developments in Mechanistic Modeling of Two-Phase Flow and Heat Transfer in Nuclear Reactor Systems", International Workshop on New Horizons in Nu­clear Reactor Thermal Hydraulics and Safety", Mumbai, India, Jan. 7-8, 2010.

PROFESSIONAL CONSULTING

  • Nooter Eriksen
  • Korea Atomic Energy Research Institute (KAERI), South Korea
  • Alcoa Technical Center
  • Westinghouse Electric Company
  • Chemical Process Industries, ESSS, Brazil
  • Canadian Nuclear Safety Commission, Canada
  • International Atomic Energy Agency (IAEA), Austria
  • Idaho National Laboratory
  • Ontario Power Generation, Canada
  • Information Systems Laboratories
  • Paul Sherrer Institute, Switzerland
  • Polytechnic Institute of Valencia, Spain
  • Kansai Electric, Kyushu Electric, Shikoku Electric, Hokkaido Electric, Japan
  • Westinghouse Electric Company
  • Scientech
  • New York Power Authority (NYPA)
  • S3 Technologies
  • ABB Atom, Sweden
  • ABB Combustion Engineering
  • Swedish Nuclear Power Inspectorate, Sweden
  • US Nuclear Regulatory Commission
  • Martin Marietta Energy Systems
  • Brookhaven National Laboratory
  • Martin Lokheed
  • Centers for Disease Control, US Department of Health
  • Oak Ridge National Laboratory
  • Sandia National Laboratories
  • Knolls Atomic Power Laboratory
  • Philadelphia Electric Company
  • Pennsylvania Power and Light Company
  • Imperial College of Science, Technology & Medicine, London, UK
  • Link-Miles Simulation Corporation
  • Gilbert/Commonwealth International
  • Long Island Light Company
  • ASEA Brown Bovery (ABB), Sweden
  • Yankee Atomic Electric Company
  • Electric Power Research Institute

OTHER PROFESSIONAL EXPERIENCE

  • Research Program Review Panel, Korea Atomic Energy Research Institute (KAERI), 2016. 
  • DOE-NE Expert Group for Fukushima Reactor Inspection Planning, 2013.
  • Panelist for Energy Security of Central Europe, Washington, DC, 2013.
  • Reviewer of the Virginia Tech proposal to establish graduate programs in Nucl. Eng., 2013.
  • Technical Program Commitee, International Conferece of Multiphase Flow (ICMF’12), 2013.
  • Peer Review Panel for the Korean Ministry of Education, Science, and Technology’s World Class University Program, December 2011, 2012.
  • DOE Nuclear Reactor Technologies Research, Development, and Demonstration Summit, 2012.
  • Organizer and Lecturer of Short Course, "Multiphase Flow and Boiling Heat Transfer; Modern Approach and Recent Advances", Knolls Atomic Power Laboratory, 2011.
  • Technical Program Committee, International Conference of Multiphase Flow (ICMF’11), 2011.
  • International Academic Expert for Royal Institute of Technology, Sweden, 2010.
  • Organizer and Chair, “Supercritical CO2 Power Cycle Symposium”, International Conference co-organized by Rensselaer Polytechnic Institute, Knolls Atomic Power Laboratory and Bettis Atomic Power Laboratory, April, 2009.
  • National Judge, Siemens Competition, 2009.
  • Co-Chairman of the International Scientific Committee, Third International Conference on Transport Phenomena in Multiphase Systems (HEAT 2005).
  • Member, Technical Program Committee, International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH Series), 1992-2018.
  • Member of Technical Program Committee, International Conference on Multiphase Flow (ICMF Series), 1995-2010.
  • Chairman of the International Scientific Committee, Second International Conference on Trans­port Phenomena in Multiphase Systems (HEAT 2002).
  • Short Course Organizer and Instructor, "Two-Phase Flow Instabilities in Nuclear Reactor Sys­tems", Madrid, Spain, 2001.
  • Short Course Organizer and Instructor, "Two-Phase Flow and Transfer in Thermal and Nuclear Systems", Vasteras, Sweden, 1999.
  • Chairman of the International Scientific Committee, First International Conference on Transport Phenomena in Multiphase Systems (HEAT 1999).
  •  NASA Review Committee, 1999.
  • Visiting Scholar, Karlsruhe Research Institute, Karlsruhe, Germany, July-August, 1998.
  • Chairman, Technical Program Committee, Seventh International Topical meeting on Nuclear Reactor Thermal Hydraulics, Saratoga Springs, 1997.
  • USNRC Review Panel for Advanced Light Water Thermal Hydraulics (ATRIG), 1994-97.
  • Chairman, ANS Severe Accident Program Review Committee, Oak Ridge National Laboratory, 1993.
  • Course Organizer and Instructor, "Two-Phase Flow and Boiling Heat Transfer", ABB Combus­tion Engineering, 1993.
  • Secretary of Organizing Committee and Co-Chair of Caucus Group, Third International Work­shop on Two-Phase Flow Fundamentals, London (UK), 1992.
  • Technical Expert, Electric Power Research Institute, 1992.
  • US NRC Expert Panel on "Research Plan for Melt Progression Issue Resolution", 1991/92.
  • US NRC NUREG/CR-5423 Expert Review Group, 1990-91.
  • Expert Review Panel, U.S. Department of Health and Human Services, 1990.
  • Technical Expert of the International Atomic Energy Agency (IAEA) in China, 1989.
  • US NRC Severe Accident Research Plan Development Program Group, 1988.
  • Lecturer, short course on "Modern Developments in Boiling Heat Transfer and Two-Phase Flow", Center for Multiphase Research, RPI, 1988 - 2008.
  • US NRC NUREG-1150 Expert Review Group, 1987-88.
  • Technical Expert of the International Atomic Energy Agency (IAEA) in Argentina, 1987.

GRADUATE STUDENT SUPERVISION

  • 40 M.S. theses in Nuclear Engineering. 
  • 32 Ph.D. thesis advisor/co-advisor in Nuclear Engineering, Mechanical Engineering, Mathematics and Engineering Physics.
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