Prediction of adiabatic bubbly flows in TRACE using the interfacial area transport equation
Type
Publication
14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14), Toronto, Canada
Justin Talley
Ph.D. 2012
Ted Worosz
Ph.D. 2015
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.