WooHyun Jung

Profile Information
Name
Dr. WooHyun Jung
Institution
University of Nevada-Las Vegas
Position
Assistant Professor
h-Index
ORCID
0009-0000-3065-8899
Biography
**PI Prof.**** WooHyun Jung**, Ph.D., is Assistant Professor in the Department of Mechanical Engineering at the University of Nevada, Las Vegas. His expertise is in the safety analysis of nuclear power plant with the basis of the thermal-hydraulics covering from the fundamental two-phase heat transfer (e.g., the boiling, the quenching, the two-phase instability, the radiative heat transfer, etc.) to the system-scale safety evaluation using system code such as MELCOR. Dr. Jung has an experience of accident analysis using MELCOR code for various reactor designs such as LWR, SMR, and gas-cooled fast reactor, which is an advanced reactor. Dr. Jung has participated in governmental-led research projects in South Korea focused on the prediction of the melt behavior under the ex-vessel phase severe accident, especially for the Fuel-Coolant Interaction with Korean Institute of Nuclear Safety (KINS, a Korean regulatory institute), the project for the development of the mitigation strategy for debris bed quenching with Korea Hydro and Nuclear Power (KHNP). He managed two DOE NEUP programs as lead-PI: “Post-DNB Thermo-mechanical Behavior of Near-term ATF Designs in Simulated Transient Conditions, DE-NE0009139 (21-24063), October 2021 – September 2025” and “Investigation of Degradation Mechanisms of Cr-coated Zirconium Alloy Cladding in Reactivity Initiated Accidents (RIA), DE-NE0008961 (20-19076), October 2020 – September 2025”. He also participated in ARC-20 project for performing accident analysis for Fast Modular Design (FMR) of General Atomics (GA) using MELCOR code. He is currently a PI of one 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, DE-NE0009487 (24-31464), August 2024 – July 2027”. Within these projects, he conducted the research from the construction of the special building and experimental facility for the severe accident experiments to the development and implementation of the physical models in the analytic codes, such as MELCOR, JASMINE or COOLAP. Dr. Jung is a member of American Nuclear Society (ANS), Korean Nuclear Society (KNS) and Korean Society of Mechanical Engineers (KSME). He has over 50 publications including, peer-reviewed journal articles, conference proceedings.
Expertise
Accident Analysis, Accident Tolerant Fuel, MELCOR, Nuclear Safety, Thermal-Hydraulics