Publications

Peer-reviewed Journals

2024

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

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

2021

Effect of layer-by-layer assembled carbon nanotube coatings on dropwise condensation heat transfer associated with non-condensable gas effect
Taeseok Kim, Doyoung Shin, Jaemin Lee, Sung Joong Kim
International Journal of Heat and Mass Transfer, 175, 121345 (2021)
DOI · 논문 보기 ↗

2020

Development of the thermal performance model using temperature gradient analysis for optimized design of steam surface condenser
Doyoung Shin, Joongoo Jeon, Taeseok Kim, Jae Hyung Park, Sung Joong Kim
International Journal of Heat and Mass Transfer, 163, 120411 (2020)
DOI · 논문 보기 ↗

2019

Local heat transfer characteristics of natural circulation flow inside an 8x8 partial spent fuel assembly under dry storage
Doyoung Shin, Jae-sung Kwon, Taeseok Kim, Sung Joong Kim
International Journal of Heat and Mass Transfer, 128, 431–442 (2019)
DOI · 논문 보기 ↗

2018

Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress
Wonjun Choi, Taeseok Kim, Joongoo Jeon, Nam Kyung Kim, Sung Joong Kim
Science and Technology of Nuclear Installations, 2018, 1–15 (2018)
DOI · 논문 보기 ↗

A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident
Taeseok Kim, Wonjun Choi, Joongoo Jeon, Nam Kyung Kim, Hoichul Jung, Sung Joong Kim
Science and Technology of Nuclear Installations, 2018, 1–12 (2018)
DOI · 논문 보기 ↗

Conferences

2022

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.

2021

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.

2020

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.

2019

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).

2018

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 DOI ↗

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 DOI ↗

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 DOI ↗

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.

2017

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.

2016

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.