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Quantum Energy Chemical Engineering Major

Prof. Tae-ho Kim 김태호

 

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Current Position

2024 ~ Present        Adjunct Professor, Quantum Energy Chemical Engineering Major, UST

2021 ~ Present        Senior Researcher, Nuclear Fuel Cycle Process Research Division, KAERI

 

Research Interests

- Nuclear Engineering

- Nuclear Fuel Cycle Process Research Division

- Advanced Fuel Cycle Technology Division

 

Education

2018 Ph.D. Nuclear Engineering, Ulsan National Institute of Science and Technology, Republic of Korea

2012 B.S. Nuclear Science and Engineering, Ulsan National Institute of Science and Technology, Republic of Korea


Work Experience

2021 ~ Present Senior Researcher, Nuclear Fuel Cycle Process Research Division, Korea Atomic Energy Research Institute

2020 ~ 2021 Assistant Scientist, Nuclear Engineering / Department of Engineering Physics, University of Wisconsin-Madison

2018 ~ 2020 Postdoctoral Researcher, Nuclear Engineering / Department of Engineering Physics, University of Wisconsin-Madison 


Projects

(On-going)

2021 ~ Present   Nuclear Fuel Cycle Process Research Division

  1. Molten salt purification and preparation for corrosion experiment in pumped and natural convection molten salt loop

    - Focus on the degradation behavior of structural materials in the molten salt loop with the various salt environment (Dissolved oxygen, moisture, nuclear fuel)


  2. Development of Molten Salt Reactor (MSR) Fuel – Chloride-based molten salt

 

(Completed)

2019 ~ 2021      Development of decontamination technologies for PWR systems, MOTIE

2019 ~ 2021      Assessment of radionuclide inventory in LILW waste, KHNP

2017 ~ 2018      Immobilization of iodine in water by layered double hydroxide, JSPS

 

Publication


(International Journal)

  • T. Kim, D.J. Shin, D. Yoon, E.-Y. Choi, and C.H. Lee, “Corrosion Behavior of Candidate Structural Materials for Molten Salt Reactors in Flowing NaCl‐MgCl2”, International Journal of Energy Research (2024)

  • T. Kim, A. Couet, S. Kim, Y. Lee, S. C. Yoo, and J. H. Kim, “In-situ electrochemical study of zirconium alloy in high temperature hydrogenated Water conditions”, Corrosion Science 173 (2020)

  • T. Kim, S. Kim, Y. Lee, N. Kim, C. B. Bahn, A. Couet, and J. H. Kim, “A study on the relationship between electronic structure and corrosion characteristics of zirconium alloy in high-temperature hydrogenated water”, Corrosion Science 157 (2019)

  • T. Kim, K. J. Choi, S. C. Yoo, Y. Lee, and J. H. Kim, “Influence of dissolved hydrogen on the early stage corrosion behavior of zirconium alloys in simulated light water reactor coolant conditions”, Corrosion Science 131 (2018)

  • T. Kim, S. Kim, C. -Y. Lee, Y. -K. Mok, and J. H. Kim, “In situ investigation of the oxidation of Zr-Nb-Cu alloy in high-temperature hydrogenated water”, Corrosion Science 119 (2017)

  • B. Hou, T. Kim*, S. Kim, C. Park, C. B. Bahn, J. Kim, S. Hong, and J. H. Kim, “Zinc Adsorption and Hydration Structures at Yttria-Stabilized Zirconia Surfaces”, Journal of Physical Chemistry C 121 (2017) (* Co-first Author)

  • T. Kim, N. H. Lee, H. K. Jung, and J. H. Kim, “Enhancement of energy performance in betavoltaic cells by optimizing self-absorption of beta particles”, International Journal of Energy Research 40 (2016)

  • T. Kim, J. Kim, K. J. Choi, S. C. Yoo, and J. H. Kim, “Effects of dissolved hydrogen on the crack-initiation and oxidation behavior of nickel-based alloys in high-temperature water”, Corrosion Science 106 (2016)

  • T. Kim, J. Kim, K. J. Choi, S. C. Yoo, S. Kim, and J. H. Kim, “Phase transformation of oxide film in zirconium alloy in high temperature hydrogenated water”, Corrosion Science 99 (2015) (Domestic Patent, Selected)

    (Book)

 

Professional Activities

 

Keynote and Guest Lecture 

 

Teaching Experience   

Honors and Awards

  • 2017.05 Outstanding Conference Paper Award, Korean Nuclear Society

  • 2016.10   Best Newcomer Poster, 20th International Conference on Water Chemistry of Nuclear Reactors Systems

  • 2015.10   Outstanding Conference Paper Award, Korean Nuclear Society

  • 2014.03   Outstanding Conference Paper Award, Korean Pressure Vessels and Piping


 

Multimedia


Students

(Postdoctoral Researchers)

 

(Ph.D. Students)

 

(MS Students)

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Contents

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