Interfacial area transport in horizontal bubbly flow with 90-degree elbow

12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Log. No. 101, Pittsburgh, PA
Seungjin Kim
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.