Characteristics of interfacial area concentration in two-phase vertical channel flow
Type
Publication
8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), Kyoto, Japan
Seungjin Kim
Capt. James McCarthy, Jr. and Cheryl E. McCarthy Head and Professor of Nuclear Engineering
My interests include thermal-hydraulics, reactor safety, two-phase flow experiments and instrumentation, interfacial area tranport modeling.