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Advanced Optical Diagnostics
Advanced Optical Diagnostics
Optical techniques for high-resolution experiments
Optical techniques for high-resolution experiments
Laser interferometry for micro-thin film
Total internal reflection for phase detection
Intergrated HSV-TIR-IR imaging
High-speed synchrotron X-ray imaging
Adavanced thermometry techniques
Adavanced thermometry techniques
High-speed infrared thermometry for surface temperature and heat flux
Rainbow schlieren deflectometry for temperature field in fluids
DEPIcT (DEtection of Phase by Infrared Thermometry)
Phosphor thermometry
Experiments
Experiments
Phase-change heat transfer fundamentals
Phase-change heat transfer fundamentals
Subcooled nucleate boiling
Departure from nucleate boiling
Slug flow boiling on downward-facing wall
Droplet-wall collision dynamics and heat transfer
Quenching/reflood heat transfer
Heat pipe for nuclear systems
Heat pipe for nuclear systems
Fork-type heat pipe for passive cooling of spent fuel pool
Heat pipe for micro/mobile and space reactor applications
ATF and CRUD effects on boiling and quenching heat transfer in LWRs
ATF and CRUD effects on boiling and quenching heat transfer in LWRs
Ultra-high heat flux cooling for fusion reactor and military
Ultra-high heat flux cooling for fusion reactor and military
Hyper-Vapotron and 3D porous structures
Hyper-Vapotron and 3D porous structures
Containment thermal-hydraulics
Containment thermal-hydraulics
film condensation and evaporation, aerosol removal
film condensation and evaporation, aerosol removal
Modeling and Simulation
Modeling and Simulation
Meso-Scale Simulation
Meso-Scale Simulation
Hybrid multiphase simulation of flow boiling heat transfer using OpenFOAM and Fluent
CFD simulation of steam extraction from surface condenser
Multiphase simulation of boiling and condensation in porous media
System-Scale Simulation
System-Scale Simulation
MARS-CUPID coupled simulation of two-phase flow heat exchanger
Safety analysis of nuclear reactor systems using MARS and SPACE
Coupled Thermo-Hydro-Mechanical-Chemical (THMC) modeling and
simulation of radionuclides transport in disposal systems of spent nuclear fuels
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