报告人：Hibiki Takashi, Chair Professor, Department of Mechanical Engineering, City University of Hong Kong.

时间：9:00-11:00 AM, 2024.7.1

地点：交大创新港1-6116

邀请人：严俊杰教授，种道彤教授

报告题目：Two-group Drift-Flux Model for Dispersed Two-phase Flows

报告简介：The two-phase flow thermo-fluid dynamics is a complicated subject due to the existence of moving and deformable interface and its interactions with the two phases. The seminar is focused on the model developed for two-phase flow in nuclear reactor and power plant. The seminar contents including Two-phase flow formulation, computational code structure, Role of interfacial area concentration, interfacial area concentration measurement, traditional interfacial area modeling approach, innovative two-group interfacial area transport equation, innovative two-group drift-flux model to predict two-group void fractions and gas velocities, Predictions of interfacial area concentration. Professor Hibiki will explain the modeling tips and demonstrate how to develop a good model for two-phase flow. Students will learn how to approach modeling of thermal-fluid phenomena and accumulate the knowledge of state-of-the-art of two-phase flow in various flow conditions and geometries.

报告人简介：Hibiki Takashi is Chair Professor, Department of Mechanical Engineering, City University of Hong Kong,Global STEM Professor of Hong Kong SAR Government and Director of Hong Kong Jockey Club STEM Laboratory of Innovative Thermo-Fluid Science. He is the Fellow of American Nuclear Society, Member of Atomic Energy Society of Japan, Member of The Japanese Society for Multiphase Flow, Member of the Heat Transfer Society of Japan, Editorial Board of the Journal of Computational Multiphase Flow, Editorial Board of International Journal of Microscale and Nanoscale Thermal and Fluid and Editorial Board of Nuclear Engineering and Technology. His research field includes Basic two-phase flow experiments and modeling, Interfacial area transport equation development，Thermal-hydraulic research at micro-gravity conditions, Critical heat flux and heat transfer in mini channels，LWR safety analysis and so on. He has developed more than 40 important constitutive equations and two-phase flow formulation to close two-phase flow equation systems and the internationally-recognized interfacial area transport equation has been implemented in ANSYS Fluent CFD code. He has gotten several honors and awards, including Award for Preeminent Monograph Award by Atomic Energy Society of Japan for modeling of distribution parameters for upward steam-water boiling flows in subchannels of a vertical rod bundle, Technology Development Award by Atomic Energy Society of Japan in recognition of development of the Nuclear Accident Consequence Assessment Code (NACAC) in Thailand, Preeminent Monograph Award, Atomic Energy Society of Japan for development of interfacial velocity correlation for benchmarking porous media based three-dimensional code for steam generator with a square rod array, Technology Development Award by Atomic Energy Society of Japan in recognition of development of advanced simulation code of complicated two-phase flows in steam generators.