Upcoming Events

Thermo Fluid Modeling Method and Tool Developments for Sodium Fast Reactor Safety

April 17, 2014 2:00PM to 3:00PM
Rui Hu (NE)
Building 203, Room D120
Thermo-fluid (i.e. thermal-hydraulics) analysis remains as one of the key disciplines essential for the safety of nuclear reactor systems. A wide range of thermal-hydraulic modeling methods have been developed or applied for reactor analysis over the past several decades.

This seminar will start with an overview of various analysis methods, their respective attributes and challenges, and followed by some recent advances in T/H modeling methods developed at Argonne for SFR safety analysis, which include a momentum source model to mimic the wire-wrap effects for coarse-mesh CFD analysis, a modeling strategy to utilize high-fidelity LES/DNS simulation results to derive mixing parameters used in subchannel analysis, and lastly a new system analysis tool development incorporating advances in physical models, software engineering, and numerical methods.