College of Engineering
University of Wisconsin - Madison

EP Wisconsin Institute of Nuclear Systems Hyeong Taek Kim

Ph.D. Student

140 Engineering Research Building
1500 Engineering Drive
Madison, WI 53706
Tel: (608)263-4447
Fax: (608)263-7451

E-mail: URL:

Nuclear Engineering and Engineering Physics

BS 1982, Nuclear Engineering, Hanyang University, Seoul, Korea
MS 1992, Nuclear Engineering, Texas A&M University, College Station, TX

Research Interests
Computational Simulation Code, Heat Transfer, Multiphase Flow, Nuclear Reactor Safety and Severe Accident Analysis

Centers and Consortia
Wisconsin Institute of Nuclear Systems

Articles and Publications
  • Kim Hyeong T., "Development of a Linearized Model for a Pressurized Water Reactor (PWR) Primary Loop",MS Project 1992 .
  • Chung Kyung N., Kim Hyeong T., "Design Concept of Korean Next Generation PWRs", The 16th Japan-Korea Atomic Industrial Forum Seminar, 1994.
  • Park Sang D., Kim Hyeong T., "Next Generation Reactor Development in Korea", The 3rd Joint Korea/French Atomic Forum round Table Meeting, 1995.
  • Park Sang D., Kim Hyeong T., "Progress in Design and Improvement of Safety System in Korean Next Generation Reactor", The 17th Japan-Korea Atomic Industrial Forum Seminar, 1995.
  • Kim H., No Hee, Park Sang D., Kim Hyeong T., "Modification of the Condensation Heat Transfer Model of RELAP5/MOD3.1 for the Simulation of Secondary Condenser", KoXSrean Nuclear Society Seminar, 1996

  • Additional Experience

    As a part of long-term manpower development program in Korea Electric Power Research Institute (KEPRI) to secure highly educated manpower in nuclear technology, Mr. Kim was assigned as a Ph.D student in nuclear safety research center of NEEP department at the University of Wisconsin Madison. Before entering NEEP department, he had been involved in Korean Next Generation Reactor Development Project at KEPRI, Taejon, Korea. Throughout his more than 15-year career with Korea Electric Power Corporation, he has experienced broad areas of nuclear power plant technology such as quality assurance, instrumentation, and thermalhydraulic load analysis, etc.

    He is expected to perform nuclear safety research such as computational simulation code upgrade, heat transfer, multiphase flow, nuclear reactor safety or severe accident analysis.

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