Research on interfacial area transport: The present and future efforts
Type
Publication
10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Paper No. A00406, Seoul, Japan
Seungjin Kim
Capt. James McCarthy, Jr. and Cheryl E. McCarthy Head and Professor of Nuclear Engineering, Chief Nuclear Officer of Purdue University
My interests include thermal-hydraulics, reactor safety, two-phase flow experiments and instrumentation, interfacial area tranport modeling.