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Kyung Mo Kim (김경모)
Kyung Mo Kim (김경모)
Assistant Professor
Next-Generation SMR in Department of Energy Engineering
Design of Innovative System for Nuclear Reactors
Thermal-hydraulic Experiments (Two-Phase Flow)
Safety Analysis of Nuclear Reactors
Prognostic/Diagnostic Platform for SMR
* Office: The Class Building Rm 514
Curriculum Vitae
(2023.04~Present) Assistant Professor, Korea Institute of Energy Technology (KENTECH), Korea
(2022.02~2023.03) Postdoctoral Research Fellow, University of Michigan, USA
(2021.02~2022.01) Visiting Scholar, Virginia Tech, USA
(2019.06~2021.02) Research Assistant Professor, UNIST, Korea
(2017.09~2019.05) Postdoctoral Research Associate, UNIST, Korea
(2013.03~2017.08) Ph.D. Department of Nuclear Engineering, UNIST, Ulsan, Korea
(2009.03~2013.02) B.S. School of Green Energy, UNIST, Ulsan, Korea
Awards/Honors/Membership
KONICOF Global Postdoc Fellowship (2021)
Best Paper Award, NURETH-16, USA (2015)
Best Student Award, NURETH-16, USA (2015)
Technical Program Committee, 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21)
Membership of Korean Nuclear Society (2012~)
American Nuclear Society (2022~)
Research publications (selected)
1) Kyung Mo Kim, Paul Hurley, Juliana P. Duarte, Physics-informed machine learning-aided framework for prediction of minimum film boiling temperature, International Journal of Heat and Mass Transfer, 191, 122839 (2022)
2) Kyung Mo Kim, In Cheol Bang, Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform, Nuclear Engineering and Technology, 53(3), 776-792 (2021)
3) Kyung Mo Kim, Dae Hyung Lee, In Cheol Bang, Analysis of natural circulation behaviors and flow instabilities of passive containment cooling system design for advanced PWR using MARS-KS code, International Journal of Heat and Mass Transfer, 147, 118982 (2020)
4) Kyung Mo Kim, In Cheol Bang, Thermal-hydraulic phenomena inside hybrid heat pipe-control rod for passive heat removal, International Journal of Heat and Mass Transfer, 119, 472-483 (2018)
5) Kyung Mo Kim, Yeong Shin Jeong, In Guk Kim, In Cheol Bang, Development of passive in-core cooling system for nuclear safety using hybrid heat pipe, Nuclear Technology, 196(3), 598-613 (2016)
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