Robert K. Salko Jr

Robert (Bob) Salko’s research interests are primarily related to computational thermal-hydraulics for both traditional light water reactors and advanced reactor systems.  This includes software development, model development, verification and validation of computer codes, modeling and simulation, code coupling, multi-scale modeling, numerical methods, high-performance computing, and quality assurance.  Some specific challenge problems that Bob has studied include departure from nucleate boiling, crud-induced localized corrosion, loss-of-coolant accident progression, boiling heat transfer and void generation, turbulent mixing, and gas transport in molten salt reactors.  Bob is the primary developer of the subchannel code, CTF, and has worked extensively with the light water reactor core simulator code, VERA, and the NEAMS MOOSE based advanced reactor systems code, SAM.