Expert Details

Multiphase Flow and Heat Transfer Technology

ID: 716249 New York, USA

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Expert has expertise in the areas of multiphase flow and heat transfer technology, particularly the measurement and modelling of vapor/liquid and solid/fluid systems. His expertise includes boiling and condensing heat transfer, two-fluid modelling, and instability analysis. Expert has applied his work to nuclear reactor safety, oil well technology, aseptic food processing, chemical processing, space power, and multiphase measurement techniques.

Served on many USNRC technical review committees.He served on EPRI peer review committees on nuclear reactor safety.Has provided extensive consulting for the Nuclear Navy.He has performed extensive industrial consulting on various multiphase flow and heat transfer applications.

Education

Year Degree Subject Institution
Year: 1971 Degree: Ph.D. Subject: Mechanical Engineering Institution: Stanford University
Year: 1966 Degree: M.E. Subject: Engineering Mechanics Institution: Columbia University
Year: 1964 Degree: M.S. Subject: Mechanical Engineering Institution: Rensselaer Polytechnic Institute
Year: 1961 Degree: B.S. Subject: Marine Engineering Institution: U.S. Merchant Marine Academy

Work History

Years Employer Title Department
Years: 1975 to Present Employer: Undisclosed Title: Department:
Responsibilities:
1994..1998: Dean of Engineering;
1991..1994: Director, Center for Multiphase Research;
1989..present: Edward E. Hood, Jr. Professor of Engineering;
1987-89: Professor, Department of Mechanical Aerospace and Nuclear Engineering and Department of Chemical Engineering;
1975-87: Chairman, Department of Nuclear Engineering & Science
Years Employer Title Department
Years: 1966 to 1975 Employer: Title: Department: Nuclear Energy
Responsibilities:
1973-75: Manager, Core & Safety Development;
1972-73: Manager, Core Development;
1971-72: Manager, Heat Transfer Mechanisms;
1966-71: Principal Development Engineer
Years Employer Title Department
Years: 1961 to 1964 Employer: Title: Engineer Department: Nuclear Navy Propulsion Systems
Responsibilities:
He worked on transient thermal-hydraulic simulations and primary shielding systems.

Additional Experience

Expert Witness Experience
Expert has extensive experience as an expert witness in numerous litigation cases involving nuclear reactor safety issues.

(1) As the primary Expert on nuclear reactor design flaws and safety scenarios leading to severe damage to a nuclear reactor (i.e., TMI-2 ).
(2) As the primary Expert on nuclear reactor power plant aging issues (e.g., embrittlement and fatigue ) associated with plant re-licensing for extended operations, as well as the associated nuclear reactor safety technology.
(3) As an Expert on PWR steam generator phase change thermal-hydraulics and failure mechanisms.

Career Accomplishments

Associations / Societies
Expert is a Fellow of the ASME and ANS, and a senior member of the AIChE and the American Society of Engineering Education. He is also a member of the National Academy of Engineering (NAE) in this country and a foreign member of the Russian Academy of Sciences (NAS).
Awards / Recognition
Expert has received numerous honors and awards, including the E.O. Lawrence Memorial Award of the USDOE; the Donald Q. Kern Award of the AIChE; the Outstanding Professional Achievement Award of USMMA; the ANS Meritorious Service Award; the ANS Outstanding Technical Achievement Award; the ANS Seaborg Medal, and the Arthur Holly Compton Award of ANS. He is an honorary Fellow of the Japan Society for the Promotion of Science.
Publications and Patents Summary
Expert was Editor of the Journal of Nuclear Engineering & Design and has authored over 300 archival publications.

Fields of Expertise

multiphase flow measurement, multiphase heat transfer, mixed flow, boiling, boiling-liquid flow, fluid dynamics, heat transfer fluid, multicomponent flow, nuclear reactor safety, two-phase flow, two-phase flow modeling, two-phase heat transfer, heat transfer technology, multiphase flowmetering, pressure drop, nuclear engineering, space power system, bubble column reactor, flow, fluid mechanics mathematical modeling, interfacial fluid mechanics, ablation, nuclear reactor design, chemical processing, Bernoulli equation, water hammer, turbulent flow, nuclear reactor, nuclear reactor technology, liquid flow through a nozzle, liquid flow measurement, hydrostatics, heat transfer, gas-liquid mass transfer operation, fluid mechanics modeling, energy conservation, condensing heat exchanger

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