Sung-Jae Yi | Thermmo Hydraulic Award | Research and Development Pioneer Award

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Dr. Sung-Jae Yi | Thermmo Hydraulic Award | Research and Development Pioneer Award

Dr. Sung-Jae Yi, Innovative safety system research div, South Korea

Dr. Sung-Jae Yi is a distinguished figure in aerospace and mechanical engineering, currently affiliated with the Korea Atomic Energy Research Institute. With a Ph.D. from the Korea Advanced Institute of Science and Technology, his expertise lies in nuclear plant analysis, thermal-hydraulic system development, and experimental research of severe accidents. As project manager for various cutting-edge facilities like VISTA, ATLAS, and SMART-ITL, he has contributed significantly to reactor design and safety. His latest endeavor focuses on pioneering a Passive Infinite Cooling Mechanism for Small Modular Reactors (SMR), reflecting his commitment to advancing nuclear technology for a sustainable future. 🚀

 

Publication Profile 

Scopus

Education

Dr. Sung-Jae Yi, a prominent figure in engineering, holds a Ph.D. in Aerospace Engineering from the Korea Advanced Institute of Science and Technology (KAIST), specializing in two-phase flow dynamics with surface tension effects. His master’s degree, also from KAIST, focused on the intricate calculations of laminar boundary layers, displaying a keen interest in fluid mechanics. With a bachelor’s degree in Mechanical Engineering from Hanyang University, he laid the foundation for his illustrious career. Yi’s academic journey symbolizes a relentless pursuit of knowledge and expertise in engineering disciplines, exemplifying a passion for innovation and discovery in the field. 📚

 

Research Experience

 

Dr. Sung-Jae Yi’s illustrious career spans decades of groundbreaking research and project management in nuclear engineering. From pioneering the Development of Nuclear Plant Analyzer (NPA) to leading the design of innovative test facilities like VISTA, ATLAS, and SMART-ITL, his contributions have significantly advanced reactor technology. Yi’s expertise extends to experimental research on severe accidents and the development of thermal-hydraulic system analysis codes. Notably, his recent focus on the “Experimental test for Hybrid SI development of APR 1400” underscores his commitment to enhancing reactor safety. Currently, he spearheads the development of a Passive Infinite Cooling Mechanism for Small Modular Reactors (SMR), symbolizing his ongoing dedication to sustainable nuclear energy solutions. ⚛️

 

Research Focus

 

Dr. Sung-Jae Yi’s research primarily focuses on thermal-hydraulic systems and safety measures in nuclear technology. His contributions range from experimental investigations to analytical studies, aiming to enhance the efficiency and safety of Small Modular Reactors (SMRs) like SMART. With expertise in areas such as containment cooling and passive safety systems, Yi’s work exemplifies a commitment to advancing nuclear engineering for sustainable energy solutions. His research endeavors encompass both theoretical analyses and practical applications, ensuring a comprehensive approach to reactor design and operation. 🌡️🔬

Publication Top Notes 

  1. Asymmetric Two-Step Thermosiphon for Containment Cooling of Small Modular Reactors by Yi, S.-J. et al. 📄 Published in Nuclear Technology, 2024. 0 Citations.
  2. Experimental and analytical investigation on SMART passive safety systems for three 2-inch SBLOCA tests using SMART-ITL by Jeon, B.G. et al. 📄 Published in Annals of Nuclear Energy, 2023. 3 Citations.
  3. Thermal-Hydraulic Research Supporting the Development of SMART by Park, H.-S. et al. 📄 Published in Nuclear Technology, 2023. 2 Citations.
  4. Investigation of two-phase natural circulation with the SMART-ITL facility for an integral type reactor by Jeon, B.G. et al. 📄 Published in Nuclear Engineering and Technology, 2022. 0 Citations.
  5. Evaluation of thermal–hydraulic characteristics of reactor coolant system and helically coiled steam generator based on performance tests with SMART-ITL by Bae, H. et al. 📄 Published in Nuclear Engineering and Design, 2021. 0 Citations.
  6. Comparison of Two Different Sized Small-Break LOCAs on the Passive Safety Injection Line Using SMART-ITL Data by Yang, J.-H. et al. 📄 Published in Nuclear Technology, 2020. 6 Citations.