Taeseok Kim, Ph.D.

Taeseok Kim graduated with a Ph.D. in Nuclear Engineering from Hanyang University. His thesis topic is condensation heat transfer. Currently, he is conducting research on a compact steam generator for SMR as a Postdoctoral Associate at MIT.

2017 ~ 2022 : PhD in Department of Nuclear Engineering, Hanyang University - Adviser : Prof. Sung Joon Kim

2011 ~ 2017 : B.A, Nuclear engineering, Hanyang University

Taeseok Kim, Sung Joong Kim, "Vertical length effect on dropwise condensation heat transfer at low heat flux - Part II: Theoretical model suitable for non-coated metal surfaces", International Journal of Heat and Mass Transfer, 226, 125510, 2024.

Taeseok Kim, Sung Joong Kim, "Vertical-length effect on dropwise condensation heat transfer at low heat flux - Part I: Experimental study", International Journal of Heat and Mass Transfer, 224, 125329, 2024

Taeseok Kim, Doyoung Shin, Jaemin Lee, Sung Joong Kim, "Effect of layer-by-layer assembled carbon nanotube coatings on dropwise condensation heat transfer associated with non-condensable gas effect", International Journal of Heat and Mass Transfer, Vol. 175, No.121345, 2021.

Doyoung Shin, Joongoo Jeon, Taeseok Kim, Jae Hyung Park, Sung Joong Kim, "Development of the thermal performance model using temperature gradient analysis for optimized design of steam surface condenser," International Journal of Heat and Mass Transfer, Vol. 163, No. 120411, 2020.

Doyoung Shin, Jae-sung Kwon, Taeseok Kim, Sung Joong Kim, "Local heat transfer characteristics of natural circulation flow inside an 8x8 partial spent fuel assembly under dry storage", International Journal of Heat and Mass Transfer, Vol. 128, pp. 431-442, 2019.

Wonjun Choi, Taeseok Kim, Joongoo Jeon, Nam Kyung Kim, Sung Joong Kim, "Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress," Science and Technology of Nuclear Installations, Vol. 2018, pp. 1-15, 2018.

Taeseok Kim, Wonjun Choi, Joongoo Jeon, Nam Kyung Kim, Hoichul Jung, Sung Joong Kim, "A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident," Science and Technology of Nuclear Installations, Vol. 2018, pp. 1-12, 2018.

Kim, T, et al. (2022). “Modified Modeling of Rivulet Flow during Dropwise Condensation Heat Transfer on a Long Vertical Tube under Atmospheric Condition.” Paper presented at the Transactions of the Korean Nuclear Society Spring Meeting.

Kim, T, et al. (2022). “EFFECT OF REDUCED CONSTRICTION RESISTANCE ON DROPWISE CONDENSATION HEAT TRANSFER OF LAYER-BY-LAYER ASSEMBLED CARBON NANOTUBE COATING ON LONG VERTICAL TUBE.” Paper presented at the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics.

Kim, T, et al. (2021). “Condensation Performance Evaluation of Evacuate containment with Xenon, Air and CO2 for Small Modular Reactor.” Paper presented at the Transactions of the Korean Nuclear Society Spring Meeting.

Kim, T, et al. (2020). “The dropwise condensation heat transfer characteristics of CNT/OTS layered surface associated with non-condensable gas effect.” Paper presented at the Transactions of the Korean Nuclear Society Autumn Meeting.

Kim, T, et al. (2020). “Experimental study of droplet characteristics in dropwise condensation along the axial length of a long vertical tube.” Paper presented at the Transactions of the Korean Nuclear Society Spring Meeting.

Kim, T, et al. (2019). “Comparison of condensation heat transfer on hydrophobic and nano-porous surface.” Paper presented at the Transactions of the Korean Nuclear Society Autumn Meeting.

Kim, T, et al. (2019). “Enhancement of condensation heat transfer by hydrophobic and nano porous surface.” Paper presented at the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics.

Kim, T, et al. (2019). “Depletion of Bubble Condensation Induced Pressure Shock using Air injection for Core-catcher System.” Paper presented at the 9th China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-9).

Kim, T, et al. (2018). “Investigation on fission products release mitigated by in-containment relief valve under SGTR accident.” Paper presented at the Transactions of the Korean Nuclear Society Spring Meeting.

Kim, T, et al. (2018). “Separate effects of wettability and wickability on pool boiling CHF.” Paper presented at NTHAS11: The Eleventh Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety Busan, Korea, November 18-21, 2018

Kim, T., Choi, W., Jeon, J., Kim, N. K., & Kim, S. J. (2018). Investigation on Fission Products Release Mitigated by In-Containment Relief Valve Under SGTR Accident. In The Proceedings of the International Conference on Nuclear Engineering (ICONE) (Vol. 7, pp. 1–6). American Society of Mechanical Engineers. Hammersmith, London, England https://doi.org/10.1115/ICONE26-82161

Choi, W., Kim, T., Jeon, J., Kim, N. K., & Kim, S. J. (2018). Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000. In The Proceedings of the International Conference on Nuclear Engineering (ICONE) (Vol. 7, pp. 1–6). American Society of Mechanical Engineers. Hammersmith, London, England https://doi.org/10.1115/ICONE26-82074

Jeon, J., Kim, N. K., Choi, W., Kim, T., & Kim, S. J. (2018). Investigation of Flammability of Hydrogen Gases With Diluent Gases Under Severe Accident Conditions Using CNFT Model. In The Proceedings of the International Conference on Nuclear Engineering (ICONE) (Vol. 9 pp. 1–9). American Society of Mechanical Engineers. Hammersmith, London, England https://doi.org/10.1115/ICONE26-81773

Kim, T, et al. (2018). “Nucleate Boiling Heat Transfer in Hydrophobic and Nano-porous Structured Surfaces Coated on a Vertical Tube.” Paper presented at 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12) Qingdao, China, October 14-18.

Kim, T, et al. (2017). “Enhanced critical heat flux in the downward facing pool boiling using layer-by-layer assembled carbon nanotube.” Paper presented at the Transactions of the Korean Nuclear Society Spring Meeting.

Kim, T, et al. (2017). “Investigation of Hydrogen Risk in the major compartments of OPR1000 using MELCOR code under SBO Scenario.” Paper presented at The 8th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics, WORTH-8.

Kim, T, et al. (2016). “Experimental study of oxidation effect on dynamic wetting phenomena.” Paper presented at the Transactions of the Korean Nuclear Society Spring Meeting.

Postdoctoral Associate, MIT  2023-present

Visiting Scholar, MIT 2022 - 2023

• Highly Compact Steam Generators for Improved Economics of Small Modular Reactors, Nuclear Energy University Program (NEUP)-US DOE, 2022 - Present

Research assistant, Hanyang University 2016-2022

• Experimental study of conjugated phase-change heat transfer PCCS implemented by MWCNT-based layer-by-layer technique, National Research Foundation (NRF)-KR MSIT, 2017-2020 -

• Research Center for Development of Innovative Original Technology of a Severe Accident FreE Multi-purpose Long-lifetime Small Modular Molten Salt Reactor (I-SAFE-MSR), National Research Foundation (NRF)-KR MSIT, 2021-present

1. Experiment

• Design experimental facilities for Two-phase hydraulics (Strong)

• Data acquisition & post-processing (Strong)

• Surface modification & characterization (Familiar)

2. Analysis

• Dropwise condensation heat transfer model on modified surface (Strong)

• Condensation heat transfer in presence of non-condensable gas (Strong)

• Boiling and condensation heat transfer in pulsating heat pipe (Familiar)

• Pool boiling critical heat flux on modified surface (Intermediate)

3. Software

• Language

  • Python (Familiar)

  • MATLAB (Familiar)

• Nuclear system code for nuclear power plant

  • MELCOR (Familiar)

  • SPACE (Familiar)

• CAD

  • CATIA (Familiar)

  • Autodesk Fusion 360 (Familiar)

  • Solidworks (Familiar)

• CFD

  • ANSYS fluent (Familiar)

  • OpenFOAM (Intermediate)

• Other tools

  • LabVIEW (Familiar)

  • OriginLab (Familiar)

Excellent presentation award, Transactions of the Korean Nuclear Society Spring Meeting, 2022

Excellent presentation award, Transactions of the Korean Nuclear Society Autumn Meeting, 2020

Best Poster Award, NTHAS11, 2018

Teaching Assistant, Hanyang University, 2017-2020

Courses: Thermal-hydraulic experiment, Applied Thermal System Design for Nuclear Energy Applications

Leader of Student Chapter of Korean Nuclear Society, 2015.9.1~2016.8.31

Student leader of Department of Nuclear Engineering, Hanyang University, 2012