报告题目：Research Activities in Thermal-hydraulics and Reactor Safety Laboratory (TRSL)
报 告 人：Dr. Seungjin Kim
Purdue University
报告时间：2018年3月5日 下午14:00-16:30 
报告地点：清华大学刘卿楼105
主 持 人：黄善仿，副教授
报告摘要：
The Thermal-hydraulics and Reactor Safety Laboratory (TRSL) of Purdue University performs research on a wide range of topics in thermal-hydraulics. Specifically, modeling of two-phase flow and fluid particle interactions in various two-phase flow conditions, two-phase flow instrumentation, reactor safety analysis, and thermal-hydraulic system code development. A brief overview of the research activities at TRSL will be given in the presentation, with focus on effects of varying orientations and flow restrictions on two-phase flow transport. An extensive high-fidelity local two-phase flow database established by the four-sensor conductivity probe in various two-phase flow conditions will be presented along with flow visualization studies. Predictive models developed to account for various geometric effects in two-phase flow transport will be presented, along with predictions made by the IATE. To demonstrate feasibility of IATE in system analysis code, results obtained in the process of developing TRACE-T, a pilot TRACE code capable of interfacial area transport equation, are presented.

报告人简介：

Dr. Seungjin Kim joined Purdue University in June, 2017 as a new Head of the School of Nuclear Engineering (SNE).  During the presentation, he will provide an overview of the School, share School's visions, and explore partnership opportunities with Purdue Nuclear Engineering on both research and education.  Dr. Kim received his Ph.D. degree in Nuclear Engineering at Purdue University in 1999.   His research expertise is in the areas of reactor thermal-hydraulics and two-phase flow experiment and modeling. He is an ANS Fellow and has served as a Chair of Thermal-Hydraulics Division of American Nuclear Society.

第262期“论坛”主请人联系方式：
黄善仿  18610811565  sfhuang@tsinghua.edu.cn