01 / THERMAL HYDRAULICS
Two-Phase Flow & Heat Transfer
Fuel-coolant interaction, high-temperature quenching, fuel dispersal, boiling heat transfer, and critical heat flux.
View research →Nuclear Engineering · Thermal Hydraulics · Reactor Safety
Understanding thermal-fluid phenomena that govern nuclear safety.
LWR · GCR · SFR · SMRReactor systems
MELCOR · MACCSSafety analysis
Boiling · Quenching · FCIThermal hydraulics
Cr-coated Zr-alloy · SiCAdvanced nuclear fuel
02 / NUCLEAR FUEL
Advanced Fuel & Cladding
Cr-coated zirconium alloys and SiC-SiCf composite cladding under normal operating and accident conditions.
View research →
03 / REACTOR SAFETY
Nuclear Reactor Safety
MELCOR and MACCS safety analysis for current and advanced reactors, including accident progression and source terms.
View research →Latest News
All news →Selected Active Projects
All projects →2026–2027
LLM-based Agentic AI Assistant to Automatically Generate the Input Deck for Severe Accident System Codes
2026–2029
Investigation of the Combined Transient and Surface Effects on ATF Critical Heat Flux
2024–2027
Understanding the Performance of SiC-SiC f Composite Cladding Architectures with Cr Coating in Normal Operating and Accident Conditions in LWRs and Advanced Reactors
Principal Investigator
WooHyun Jung, Ph.D.
Assistant Professor of Mechanical Engineering at UNLV. Research interests include nuclear reactor thermal-hydraulics, two-phase flow and heat transfer, advanced fuel-cladding systems, and reactor safety analysis.
Interested in nuclear thermal-hydraulics?
Learn about research opportunities in experiments, safety analysis, and AI-enabled nuclear engineering.