WooHyun Jung, Ph.D., is an assistant professor in the Department of Mechanical Engineering at UNLV. His expertise is in the safety analysis of nuclear power plants, grounded in thermal-hydraulics — spanning from fundamental two-phase heat transfer (boiling, quenching, two-phase instability, radiative heat transfer, etc.) to system-scale safety evaluation using system codes such as MELCOR.

Jung has extensive experience in accident analysis using the MELCOR code for various reactor designs, including LWRs, SMRs, and gas-cooled fast reactors. He participated in a government-led research project in South Korea focused on predicting melt behavior during the ex-vessel phase of severe accidents — particularly fuel-coolant Interaction — as well as a related project developing mitigation strategies for debris bed quenching. He managed two programs as lead PI for the Department of Energy’s (DOE) Nuclear Energy University Program (NEUP): "Post-DNB Thermo-mechanical Behavior of Near-term ATF Designs in Simulated Transient Conditions” (2021–25) and "Investigation of Degradation Mechanisms of Cr-coated Zirconium Alloy Cladding in Reactivity Initiated Accidents (RIA)" (2020–25). He also participated in the ARC-20 project, performing accident analysis for General Atomics' Fast Modular Reactor (FMR) design using the MELCOR code. 

He is currently lead PI of the DOE NEUP program "Understanding the Performance of SiC-SiCf Composite Cladding Architectures with Cr Coating in Normal Operating and Accident Conditions in LWRs and Advanced Reactors" (2024–27) and the Genesis Mission project "LLM-based Agentic AI Assistant to Automatically Generate the Input Deck for Severe Accident System Codes" (2026–27). Across these projects, he has conducted research ranging from the construction of specialized buildings and experimental facilities for severe accident experiments to AI agent development for accelerated safety analysis using system codes such as MELCOR, JASMINE, and COOLAP.