Professor

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  • Professor

KIM, Yong Soo

Research Interests

  • Nuclear reactor material
  • Nuclear fuel performance analysis
  • Advanced Nuclear fuel
  • Applied plasma engineering
  • Decontamination and decommissioning of nuclear power plant
  • Radiation damage by high energy particles
  • Development of neutron/gamma complex radiation shielding materials
  • Pyroprocessing technology

Lectures

  • Applied Materials and Science
  • Basic Nuclear Engineering Laboratory
  • Nuclear Reactor Materials and Science
  • Applied Thermodynamics

Education

  • B.S., Nuclear Engineering, Hanyang Univ., 1983
  • M.S., Nuclear Engineering, Hanyang Univ., 1987
  • Ph.D., Nuclear Engineering, University of California, Berkeley, 1992
  • LBNL (Lawrence Brkeley National Lab.), 1989 - 1992

Experiences

  • 1994~Present Professor, Department of Nuclear Engineering, Hanyang University
  • 1999~2001 Chief, Nuclear plant technology Laboratory in Hanyang University
  • 2011~2013 Head of Department of public relations in Accreditation Board for Engineering Education of Korea
  • 1994~Present Member of the Korean Institute of Surface Engineering
  • 1994~Present Memmber of the Korean Institute of Metals and Materials
  • 1998~Present Member of the American Nuclear Society (ANS)
  • 2002~Present Member of the committee, Korean Nuclear Society (KNS)
  • 2003~Present General Executive, Korea Nuclear Equipment Qualifiction Association (KNEQA)
  • 2004~Present Director, IAEA Designated Center for Nuclear Materials DataBase
  • 2007~Present General Executive, Korean Radioactive Waste Society (KRS)
  • 2011~Present Head of External Affairs and Development Office in Hanyang University
  • 2013~Present Head of Decontamination & Decommissioning Safety Research Center
  • 2014~Present CTO, HNEnertech

Major Research Projects

  • Performance analysis of high burn-up/extended fuel cycle
  • Development and operation of property DB for nuclear reactor materials
  • Development of light-weight and high-efficiency shielding materials
  • Research on etching of metallic radioactive waste in NF3 plasma
  • Evaluation of long term integrity characteristics on structural components in PRIDE
  • Research on component materials in the TOKAMAK type fusion reactor
  • Development of technology and regulatory policy for decontamination and decommissioning of nuclear power plant

Lectures

  • Applied Materials and Science
  • Basic Nuclear Engineering Laboratory
  • Nuclear Reactor Materials and Science
  • Applied Thermodynamics

Major Research Papers

  • Y.S. Kim, J.S. Kim, Y.J. Kim, D.H. Kook,

    A study on hydride reorientation of Zircaloy-4 cladding tube under stress, J. Nucl. Mater, 456 (2015) 246-252

  • Y.S. Kim, J.S. Kim, T.H.Kim, D.H. Kook,

    Effects of hydride morphology on the embrittlement of Zircaloy-4 cladding, J. Nucl. Mater, 456 (2015) 235-245

  • Y.S. Kim, Y.H. Jeong, S.B. Son,

    A study on the effects of dissolved hydrogen on zirconium alloys corrosion, J. Nucl. Mater, 444 (2014) 349-355

  • Y.S. Kim, J.S. Kim,

    Effect of thermal history on the terminal solid solubility of hydrogen in Zircaloy-4, J. Nucl. Mater, 39 (2014) 16442-16449

  • Y.S. Kim, J.W. Choi, J.S. Kim,

    REVIEW OF SPENT FUEL INTEGRITY EVALUATION FOR DRY STORAGE, Nuclear Engineering and Technology, 45(2013) 115-124

  • Y.S. Kim, I.J. Cho, S.Y. Park, B.H. Heung,

    Equilibrium-Based Computation on High Temperature Reaction Behaviors of a Cs-U-O System with Oxidation and Reduct, 10 (2013) 1714-1721

  • Y.S. Kim, J.S. Kim, H.K Yoon, D.H. Kook,

    A study on the initial characteristics of domestic spent nuclear fuels for long term dry storage, Nuclear Engineering and Technology, 45 (2013) 377-384

  • Y.S. Kim, D.H. Kook, D.K. Cho, M.S. Lee, J.Y. Lee, H.J. Choi,

    Pyroprocess waste disposal system and dose calculation, NUCLEAR ENGINEERING AND TECHNOLOGY, 44 (2012)483-490

  • Y.S. Kim, D.H. Kook, D.K Cho, H.J. Choi,

    RADIATION SAFETY EVALUATION OF THE HANARO RESEARCH REACTOR SPENT FUEL DISPOSAL SYSTEM, NUCLEAR TECHNOLOGY & RADIATION PROTECTION, 26 (2011) 50-57

  • Y.S. Kim, Y.H. Jeong, J.N. Jang,

    Stress measurements during thin film zirconium oxide growth, J. Nucl. Mater, 412 (2011) 217–220

  • Y.S. Kim, T.D. Seo, H.S. Lee, C.S Song,

    A STUDY ON THE AGING DEGRADATION OF ETHYLENE-PROPYLENE-DIENE MONOMER (EPDM) UNDER LOCACONDITION, Nuclear Engineering and Technology, 43 (2011) 279-286

  • Y.S. Kim, I.J Cho, K.T. Park, S.K. Lee, J.H. Lee,

    Rapid and cost-effective method for synthesizing zirconium silicides, 165 (2010) 728-734

  • Y.S. Kim, S.H. Jeon, C.H. Jung,

    Cold Plasma Processing and Plasma Chemistry of Metallic Cobalt Surface, Plasma Chemistry, and Plasma Processing, 28 (2008) 617-628

  • Y.S. Kim, C.B. Lee,

    Two-step two-stage fission gas release model, J. Nucl. Mater, 374 (2008) 431–436

  • Y.S. Kim, D.J. Kim, S.H. Kim, J.H. Kim, J.H. Yang, Y.W. Lee,

    The Linear Thermal Expansion and the Thermal Diffusivity Measurements for Near-stoichiometric (U,Ce)O2 Solid Solutions, THERMOCHIMICA ACTA, 441 (2006) 127-131

  • Y.S. Kim, D.J. Kim, J.H. Yang, S.H. Kim, H.S. Kim,

    The Effects of the Physical States of a Simulated Fission Product on the Linear Thermal Expansion of (U0.924Ce0.076) O2, Journal of Alloys and Compounds, 421 (2006) 151-155

  • Y.S. Kim, Y.W. Lee, D.J. Kim,

    The thermal conductivity and lattice parameter measurements in a low Ce content (UCe)O2 mixed oxide, J. Nucl. Mater., 342 (2005) 192-196

  • Y.S. Kim, Y.D. Seo, M. Koo,

    Decontamination of Metal Surface by Reactive Cold Plasma Removal of Cobalt, J. Nucl. Sci. Technol., 41 (2004) 1100-1105

  • Y.S. Kim,

    Theoretical analysis of two-stage fission gas release processes: grain lattice and grain boundary diffusion, J. Nucl. Mater., 326 (2004) 97-105

  • Y.S. Kim, S.H. Jeon, C.H. Jung,

    W.Z. Oh, Fluorination reaction of uranium dioxide in CF4/O2/N2 r.f. plasma, Annals of Nuclear Energy, 30 (2003) 1199-1209

  • Y. Kim, S. Kim, J. Chung, and Y. Chung,

    Effects of Sn and Nb on Massive Hydriding Kinetics of Zirconium Alloys, J. Nucl. Mater., 279 (2000) 335-343

  • Y. Kim and S. Kim,

    Kinetic studies on massive hydriding of commercial zirconium alloy tubing, J. Nucl. Mater., 270 (1999) 147-153

  • Y. Kim, J. Min, K. Bae, and M. Yang,

    Uranium dioxide reaction in CF4/O2 RF plasma, J. Nucl. Mater., 270 (1999) 253-258

  • Y. Kim and D. R. Olander,

    Reaction of β-SiC with Thermal Atomic Hydrogen by MMBMS, Surface Science, 313 (1994) 399-416


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