The Thermal-Hydraulic Research Laboratory (THRL) advances the frontier of nuclear engineering by conducting fundamental and applied research on multi-scale & multi-physics flow phenomena. Our team focuses on developing innovative thermal-hydraulic solutions for both existing and next-generation nuclear reactors, including Light Water Reactors (LWRs), High-Temperature Gas-Cooled Reactors (HTGRs), Molten Salt Reactors (MSRs), Liquid Metal Reactors (LMRs), and heat pipe microreactors.
We pride ourselves on strong collaborations with academic institutions, national laboratories, and industry partners around the globe. By integrating state-of-the-art experimental facilities with cutting-edge computational tools, we enable deeper insights into complex flow and heat transfer phenomena that drive safer, more efficient nuclear energy systems.
Our Laboratory
Located in the University Service Building (USB), the THRL occupies a 14,000 ft² research space with comprehensive services and utilities. Our lab includes:
- Two fully equipped machine shops for custom fabrication of components and test sections
- Cold and Deionized Water Systems
- Compressed Air, Helium, and Nitrogen supplies
- Low/High Voltage AC/DC Power resources
- Flexible data acquisition and control systems
These capabilities allow us to design, build, and operate a wide range of phenomenological, separate effects, and integral effects test facilities that address the thermal-hydraulic challenges inherent in diverse reactor technologies.
Instrumentation
Our experimental capabilities feature state-of-the-art equipment for high-fidelity flow and heat transfer measurements:
- Multiple low- and high-power lasers for flow visualization and diagnostics
- Particle Image Velocimetry (PIV) systems with high-speed, high-resolution cameras
- Laser Doppler Velocimetry (LDV)
- Distributed Temperature Sensors (DTS) and Laser-Induced Fluorescence (LIF) for advanced temperature measurement
These tools enable both high spatial and temporal re
solution in flow measurement
and thermal analysis, underpinning our work on complex reactor geometries and advanced reactor concepts.
Computational Tools and Software
To complement our experimental research, we employ a wide variety of system-level and Computational Fluid Dynamics (CFD) codes:
System and Subchannel Codes
- RELAP5, RELAP5-3D
- MELCOR
- GOTHIC
- MAAP
- RETRAN
- TRACE
- COBRA-TF
- CATHARE
CFD Codes
- ANSYS Fluent
- ANSYS CFX
- CD-ADAPCO StarCCM+
- Nek5000
- OpenFOAM
- Saturne
- Lattice Boltzmann Method (LBM)–based codes
This suite of computational tools, combined with our experimental expertise, provides robust modeling and simulation capabilities that guide design, safety assessments, and operational strategies for a wide range of reactor concepts.
Through innovative experimental research, high-fidelity computational analyses, and interdisciplinary collaboration, the Thermal-Hydraulic Research Laboratory is shaping the future of nuclear energy. We welcome opportunities to partner with researchers and industry leaders who share our dedication to advancing nuclear technology for a safer, more sustainable world.
