Research Project Topics
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Separate Effects of Curvature on Two-Phase Flow
Experiments and analysis of two-phase flow subjected to centrifugal forces
Objective Flow Regime Identification for Inclined Two-Phase Flows
Experiments and machine learning applications for flow regime identification
Wire-Wrapped Rod Bundle Experiments and Pressure Drop Modeling
Wire-wrapped rod bundles are often proposed for advanced nuclear reactors operating in a fast neutron spectrum, as designers seek to minimize neutron scattering by tightly packing the fuel pins into a hexagonal lattice.
Separate Effects of Inclination on Two-Phase Flow
Experiments and analysis of changing body force direction on two-phase flows
Experimental Study and CFD Design Tool Development for the Cartridge Loop in the Versatile Test Reactor (VTR)
Scaling analysis and Computational Fluid Dynamics analysis of the Versatile Test Reactor
Hybrid Subcritical Testbed (HYST) Facility Design and Data Analysis
Purdue is assisting Niowave, Inc in the design and analysis of a new test faciliy
Jet Impingement Model Evaluation and Development
Analysis of non-conservatisms in exisiting jet impingement models
Identification of Plug Bubbles by Segmentation of Images using a Residual Neural Network
Development of a method of bubble identification using a neural network
Experiments for the Development of TRACE with Interfacial Area Transport Models
Developing a database of local two-phase flow parameters for development of interfacial area transport models.
Horizontal Bubbly Two-Phase Flow with Flow Restrictions
Analysis of pressure drop and interfacial area transport for horizontal two-phase flow through different elbows.
Large Diameter Horizontal Two-Phase Flow
Experiments and analysis on the scalability of horizontal two-phase closure relations
Objective Flow Regime Identification via Ultrasound
Analysis using ultrasonic signal and Symbolic Dynamic Filtering (SDF) to determine the flow structure.
Two-Phase Flow in Combinatorial Flow Channels
Experimental studies to understand the effect of flow restrictions on two-phase flow and associated dynamic models.
Spacer Grid Separate Effects
Fundamental experiments on the separate effects of rob bundle geometry on two-phase thermal-hydraulics.
Spacer Grid Thermal Hydraulics Program
Fundamental experiments of rob bundle thermal-hydraulics for system codes in the Nuclear Industry.
Small Diameter Horizontal Two-Phase Flow
Experiments and analysis of horizontal two-phase flow for multi-phase computational fluid dynamic benchmarking.
Air-Ingress in VHTR
Investigations on the postualated Depressurized Loss of Forced Circulation event for the Very High Temperature Gas-Cooled Reactors (VHTR).