Hyo Jun An, Jae Hyung Park, JinHo Song, Sung Joong Kim, "Investigation of Effect of Metal Containment Vessel Wall Thickness on Initial Decay Heat Removal with Flooding Safety System using MELCOR Code", The 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 14), Vancouver, Canada, August 25-28, 2024

Cheolwoong Kim, Jae Hyung Park, Joon Young Bae, Chang Hyun Song, Yongjun Lee, Sung Joong Kim, "Understanding MELCOR CVH/FL Governing Equations for Future AI Application", The 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 14), Vancouver, Canada, August 25-28, 2024

Beomjin Jeong, Geon Hyeong Lee, Geunyoung Byeon, Namgook Kim, Sung Joong Kim, "Numerical and Experimental Study of Radiative Heat Transfer with Radiation Shielding for Application of Metal Containment Vessel Design in Small Modular Reactor Development", The 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 14), Vancouver, Canada, August 25-28, 2024

Jihun Im, Jae Hyung Park, Won Jun Choi, Sangtae Kim, Sung Joong Kim, "Investigating the Influence of PCM Properties, Containment Geometry, and Initial Conditions on the Transient behavior of a PCM-Based Heat Removal System for Passive Molten Salt Fast Reactor", The 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 14), Vancouver, Canada, August 25-28, 2024

Yongjun Lee, Chang Hyun Songa, Joon young Bae, JinHo Songa, Sung Joong Kim* , "The Impact of Thermal-Hydraulic Information on Nuclear Fission Product Behavior Simulation Using the SIRIUS Module in the CINEMA Code", The 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 14), Vancouver, Canada, August 25-28, 2024

Geunyoung Byeon, Beomjin Jeong, Namgook Kim, Geon Hyeong Lee, JinHo Song, Sung Joong Kim* , "Preliminary Assessment of Cooling Performance in Small Modular Reactor Metal Containment Vessel According to the Filling Gas Types", The 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 14), Vancouver, Canada, August 25-28, 2024

Won Jun Choi, Jae Hyung Park, Seung Gyu Hyeon, Jinho Song, and Sung Joong Kim, "Experimental Investigation on Helium Drag Effect on the Natural Circulation Enhancement for Passive Molten Salt Fast Reactor (PMFR)", The 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 14), Vancouver, Canada, August 25-28, 2024

Chang Hyun Song, JinHo Song, Sung Joong Kim, “MELCOR Analysis of Accident Mitigation Capability of Flooding Safety System in Korean i-SMR under hypothetical Loss of Coolant Accident ”, 2024 International Congress on Advances in Nuclear Power Plants (ICAPP), Las Vegas, USA, June 16–19, 2024

Yun Sik Cho, Hyo Jun Ahn, Do Won Lee, Sung Joong Kim, “Preliminary Experiment for Validation of Fission Product Flotation System in Passive Molten Salt Fast Reactor”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Won Jun Choi, Jae Hyung Park, Seung Gyu Hyeon, JinHo Song, Sung Joong Kim, “Sensitivity Assessment of Gas Injection Effect on the Natural Circulation Performance through Adiabatic Two-Phase Experiment ”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Ye Hwan Chun, Sang Mo An, Sung-Il Kim, Yun Sik Cho, Juhyeong Lee, Won Jun Choi, Jihun Im, JinHo Song, Sung Joong Kim, “Preliminary CFD Analysis of Spreading and Solidification of FLiNaK and KCl-UCl3”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Se Hee Kwon, Won Jun Choi, Chang Hyun Song, JinHo Song, Sung Joong Kim, “Performance Evaluation of Conceptual Hybrid Safety Injection Tank under SBO Accident by Using MELCOR Code”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Geunyoung Byeon, Hyo Jun An, Chang Hyun Song, JinHo Song, Sung Joong Kim, “Feasibility Analysis of Cooling Performance of Passive Containment Cooling System Applicable for OPR1000”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Joon Young Bae, JinHo Song, Chang Hyun Song, Injae Kim, Sung Joong Kim, Jeong Ik Lee, Miro Seo, Tae-Young Shin, “Autoregressive Multivariate Time Series Forecasting of Total Loss of Component Cooling Water Accident Sequences Calculated by Modular Accident Analysis Program, Inspired by Video Prediction Methods Using Deep Learning”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Beomjin Jeong, Geon Hyeong Lee, Geunyoung Byeon, Namgook Kim, Sung Joong Kim, “An Experimental Study on the Effect of Thermal Radiation Shielding within a Metal Containment Vessel of Small Modular Reactors”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Jihun Im, Jae Hyung Park, Won Jun Choi, Sung Joong Kim, “Preliminary Design of System-integrated Heat Exchangers for Passive Molten Salt Fast Reactor”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Jae Hyung Park, Hyo Jun An, Jihun Im, Hongsik Kim, JinHo Song, Sung Joong Kim, “Development of Long-term Safety Assessment Methodology for Multi-Module SMR by Using Simplified Model of Flooding Safety System”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Cheolwoong Kim, Joon Young Bae, Chang Hyun Song, JinHo Song, Joongoo Jeon, Sung Joong Kim, “Preliminary Analysis for Applicability of Physics Informed Neural Networks (PINNs) on Water Flow Analysis in Tanks”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Juhyeong Lee, Yonghee Kim, Sangtae Kim, Sung Joong Kim, “Impact of Reactor Height on Natural Circulation Performance and Thermal Characteristics in Passive Molten Salt Fast Reactors”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Seung Gyu Hyeon, Jae Hyung Park, Hyo Jun An, JinHo Song, Sung Joong Kim, “Sensitivity Assessment of Natural Circulation SMR Applicable to Maritime Ships Using MARS-KS code”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Hyo Jun An, Jae Hyung Park, JinHo Song, Sung Joong Kim, “Sensiticity Analysis for Metal Containment Vessel Wall Thickness to Accommodate Flooding Safety System using MELCOR Code.”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Chang Hyun Song, JinHo Song, Sang Ho Kim, Jaehyun Ham, Sung Joong Kim, “Preliminary MELCOR analysis of i-SMR under hypothetical loss of coolant accident”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Yongjun Lee, Chang Hyun Song, Joonyoung Bae, JinHo Song, Sung Joong Kim, “Effect of Thermal-hydraulic Coupling on the Fission Products Behavior by Using SIRIUS Modules in CINEMA Code”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 8–10, 2024

Jihun lm, Jae Hyung Park, Won Jun Choi, Sangtae Kim, Younghee Kim, Youngsoo Yoon, Sung Joong Kim, "Preliminary Analysis and Design of the Heat Exchangers for the Passive Molten Salt Fast Reactor (PMFR)", The 10th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-10), Jeju, Korea, November, 2023.

Juhyeong Lee, Won Jun Choi, Younghee Kim, Sangtae Kim, Minseop Song, Sung Joong Kim, "Transient Simulation of Natural Circulation in a Passive Molten Salt Fast Reactor (PMFR) Using OpenFOAM", The 10th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-10), Jeju, Korea, November, 2023.

Seung Gyu Hyeon, Jae Hyung Park, Hyo Jun An, Sung Joong Kim, "Feasibility Assessment of Natural Circulation SMRs Behavior Applicable to Nuclear Submarine", The 10th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-10), Jeju, Korea, November, 2023.

Yongjun Lee, Chang Hyun Song, Joon Young Bae, JinHo Song, Sung Joong Kim, "Sensitivity Analysis on Aerosol-Related Variable of SIRIUS Module for Deriving CINEMA Code Uncertainty Variables", The 10th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-10), Jeju, Korea, November, 2023.

Geunyoung Byeon, Beomjin Jeong, Namgook Kim, Geon Hyeong Lee, Sung Joong Kim, "Preliminary Investigation of Cooling Performance According to the Type of Filling Gas for application of Metal Containment Vessel design in Small Modular Reactor development", The 10th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-10), Jeju, Korea, November, 2023.

Beomjin Jeong, Geunyoung Byeon, Namgook Kim, Geon Hyeong Lee, Sung Joong Kim, "Experimental study of Radiative Heat Transfer with Radiation Shielding for application of Metal Containment Vessel design in Small Modular Reactor development", The 10th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-10), Jeju, Korea, November, 2023.

Geunyoung Byeon, Beomjin Jeong, Namgook Kim, Geon Hyeong Lee, Sung Joong Kim, "Preliminary Study of Cooling Performance on Metal Containment Vessel design with Thermal Radiation Shielding for Application of Small Modular Reactor Development”, Transactions of the Korean Nuclear Society Autumn Meeting Gyeongju, Korea, October, 2023.

Chang Hyun Song, Jae Hyung Park, and Sung Joong Kim, “Feasibility Analysis of Flooding Safety System of I-SMR with code”, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20), Washington D.C., USA, August, 2023.

Namgook Kim, Beomjin Jeong, Geunyoung Byeon, Sung Joong Kim, “Subcooling on flow boiling critical heat flux enhancement of Cr-coated tube under low pressure”, Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May, 2023.

Chang Hyun Song, Jae Hyung Park, Sung Joong Kim, “MELCOR Analysis for Core Coolability by Flooding Safety System Applicable for i-SMR”, Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May, 2023.

Namgook Kim, Jae Hyung Park, Jihun Lim, Hyo Jun An, Sung Joong Kim, “Effects of Truly Optimized PWR Lattice core design on Reactor Power and Critical Heat Flux in a Natural Circulation Small Modular Reactor”, Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May, 2023.

Yun Sik Cho, Jae Hyung Park, Jihun Lim, Juhyeong Lee, Wonjun Choi, Sung Joong Kim, “Feasibility Evaluation of the Passive Molten Salt Fast Reactor (PMFR) Concept: A Parametric Sensitivity Analysis of Helical Coil Heat Exchangers and Supercritical Carbon Dioxide Power Conversion Systems  “, Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May, 2023.

Chang Hyun Song, Jae Hyung Park, Hyo Jun An, Sung Joong Kim, “Investigation for Effective Flow Path Designed for Flooding Safety System by Using MELCOR code”, Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May, 2023.

Yun Sik Cho, Sung Joong Kim, “Development of Simulation Technique for Crust Formation calculation using Rigid Body Dynamics Model in Moving Particle Semi-implicit”, Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May, 2023.

Yun Sik Cho, Jae Hyung Park, Jihun Lim, Juhyeong Lee, Wonjun Choi, Sung Joong Kim, “Assessment of Helium Bubbling Effect in terms of Natural Circulation Performance by Using Experiment and CFD”, Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May, 2023.

Juhyeong Lee, Sung Joong Kim, “Analysis of natural circulation characteristics of passive molten salt fast reactor by using OpenFOAM simulation”, Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May, 2023.

Chang Hyun Song, Jae Hyung Park, Hyo Jun An, Sung Joong Kim, “Effective flooding time investigation for the flooding safety system valve determination assessed by MELCOR code”, 2023 International Congress on Advances in Nuclear Power Plants in conjunction with 38th Korea Atomic Power Annual Conference, Gyeongju, South Korea, April 23–27, 2023

Chang Hyun Song, Geon Hyeong Lee, Sung Joong Kim, “CFD ANALYSIS OF RADIATIVE HEAT TRANSFER BETWEEN REACTOR PRESSURE VESSEL AND METAL CONTAINMENT VESSEL”, 2023 International Congress on Advances in Nuclear Power Plants in conjunction with 38th Korea Atomic Power Annual Conference, Gyeongju, South Korea, April 23–27, 2023

Yun Sik Cho, Jae Hyung Park, Jihun Lim, Juhyeong Lee, Wonjun Choi, Sung Joong Kim, “Assessment of Helium Bubble Lift during Natural Circulation for Passive Molten Salt Fast Reactor (PMFR) by Using Experiment and CFD”, 2023 International Congress on Advances in Nuclear Power Plants in conjunction with 38th Korea Atomic Power Annual Conference, Gyeongju, South Korea, April 23–27, 2023

Jihun Lim, Juhyeong Lee, Sung Joong Kim, “Investigation of natural circulation characteristics in passive molten fast reactor by using 3-dimensional OpenFOAM simulation”, 2023 International Congress on Advances in Nuclear Power Plants in conjunction with 38th Korea Atomic Power Annual Conference, Gyeongju, South Korea, April 23–27, 2023

Namgook Kim, Yun Sik Cho, Jae Hyung Park, Jihun Lim, Juhyeong Lee, Wonjun Choi, Sung Joong Kim, “Development of Conceptual Design and Preliminary Experiment for Flotation System using Helium Bubbling Technique in Passive Molten Salt Fast Reactor Primary System”, 2023 International Congress on Advances in Nuclear Power Plants in conjunction with 38th Korea Atomic Power Annual Conference, Gyeongju, South Korea, April 23–27, 2023

Yun Sik Cho, Jae Hyung Park, Jihun Lim, Juhyeong Lee, Wonjun Choi, Sung Joong Kim, “Conceptual Design of a Passive Safety System Triggered by Inactivation of the Active Systems for the Passive Molten Salt Fast Reactor.”, 2023 International Congress on Advances in Nuclear Power Plants in conjunction with 38th Korea Atomic Power Annual Conference, Gyeongju, South Korea, April 23–27, 2023

Taeseok Kim, Jae Hyung Park, Jihun Lim, Sung Joong Kim, “Conceptual Design of a Passive Safety System Triggered by Inactivation of the Helium Bubbling System for the Passive Molten Salt Fast Reactor”, NTHAS12: The 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, Miyazaki, Japan, November, 2022

Taeseok Kim, Yun Sik Cho, Jae Hyung Park, Jihun Lim, Juhyeong Lee, Wonjun Choi, Sung Joong Kim, “Conceptual design of thermal-hydraulics and safety systems for passive molten salt fast reactor”, NTHAS12: The 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, Miyazaki, Japan, November, 2022

Taeseok Kim, Geunyoung Byeon, Jae Hyung Park, Sung Joong Kim, “Modeling of Rivulet and Droplet Heat Trnasfer Incorporating Vertical Length Effect under Dropwise Condensation”, NTHAS12: The 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, Miyazaki, Japan, November, 2022

Taeseok Kim, Juhyeong Lee, Sung Joong Kim, “Preliminary 3-dimensional analysis for natural circulation of PMFR by using OpenFOAM code”, Transactions of the Korean Nuclear Society Autumn meeting, Changwon, Korea, October, 2022

Wonjun Choi, Chang Hyun Song, Joon Young Bae, Sung Joong Kim, “Benchmarking of PHEBUS FPT0 experiment by using CINEMA and MELCOR code”, Transactions of the Korean Nuclear Society Autumn meeting, Changwon, Korea, October, 2022

Chang Hyun Song, Jae Hyung Park, Hyo Jun An, Sung Joong Kim, “Feasibility analysis of flooding safety system of ATOM during early phase of accident by using MELCOR code”, Transactions of the Korean Nuclear Society Autumn meeting, Changwon, Korea, October, 2022

Yun Sik Cho, Jae Hyung Park, Jihun Lim, Juhyeong Lee, Wonjun Choi, Sung Joong Kim, “Preliminary Analysis of Helium Bubbling Effect on Two-phase Flow for Passive Molten Salt Fast Reactor (PMFR)”, Transactions of the Korean Nuclear Society Autumn meeting, Changwon, Korea, October, 2022

Taeseok Kim, Geon Hyeong Lee, Sung Joong Kim, “CFD Evaluation of Radiative and Natural Convective Conjugate Heat Transfer in the Gap Space between Small Modular Reactor Vessel and Metal Containment during Normal Operation”, Transactions of the Korean Nuclear Society Autumn meeting, Changwon, Korea, October, 2022

Wonjun Choi, Juhyeong Lee, Sung Joong Kim, “Preliminary MELCOR analysis for in-containment relief valve and pool scrubbing system to mitigate fission product bypass under thermally-induced steam generator tube rupture accident in OPR1000”, Transactions of the Korean Nuclear Society Autumn meeting, Changwon, Korea, October, 2022

Joongoo Jeon, Taeseok Kim, Chang Hyun Song, Geon Hyeong Lee, Sung Joong Kim, “Numerical Assessment of Thermal Radiation Shielding Effects in Small Modular Reactor with Double-vessel Structure during Normal Operation Conditions”, The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13), Taichung, Taiwan, September 4–9, 2022

Wonjun Choi, Juhyeong Lee, Sung Joong Kim, “Feasibility study of in-containment relief valve and pool scrubbing system in response to the steam generator tube rupture accident in OPR1000”, The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13), Taichung, Taiwan, September 4–9, 2022

Doyoung Shin, Taeseok Kim, Jae Hyung Park, Jihun Lim, Sung Joong Kim, “Preliminary Study on the Alternative Passive Safety Systems Triggered by Decompression of the Helium Bubbling System for the Molten Salt Reactor”, The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13), Taichung, Taiwan, September 4–9, 2022

Wonjun Choi, Chang Hyun Song, Joon Young Bae, Sung Joong Kim, “Development of classification model for source term category grouping of accident sequences by using recurrent neural network”, The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13), Taichung, Taiwan, September 4–9, 2022

Taeseok Kim, Sung Joong Kim, “Modified Modeling of Rivulet Flow during Dropwise Condensation Heat Transfer on a Long Vertical Tube under Atmospheric Condition”, Transactions of the Korean Nuclear Society Autumn meeting, Changwon, Korea, October, 2022

Jae Hyung Park, Jihun Lim, Sung Joong Kim, “Preliminary Study of Conceptual Design of Passive Residual Heat Removal System for PMFR Safety”, Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May, 2022.

Taeseok Kim, Jae Hyung Park, Jihun Lim, Wonjun Choi, Sung Joong Kim, “Design Concepts and Requirements of Passive Molten Salt Fast Reactor (PMFR) “, Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May, 2022.

Doyoung Shin, Jihun Lim, Sung Joong Kim, “PRELIMINARY STUDY ON OPTIMIZATION OF DRY AIR-COOLED SUPERCRITICAL CO2 CYCLE WITH ENVIRONMENT TEMPERATURE FOR SMALL MODULAR REACTOR APPLICATION”, The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13), Taichung, Taiwan, September 4–9, 2022

Doyoung Shin, Taeseok Kim, Jae Hyung Park, Sung Joong Kim, “FEASIBILITY ASSESSMENT OF LONG-TERM COOLABILITY OF ADVANCED SMALL MODULAR REACTOR IN MULTIPLE MODULE CONFIGURATION”, The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13), Taichung, Taiwan, September 4–9, 2022

Doyoung Shin, Taeseok Kim, Sung Joong Kim, “Effect of reduced constriction resistance on dropwise condensation heat transfer of layer-by-layer assembled carbon nanotube coating on long vertical tube”, The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13), Taichung, Taiwan, September 4–9, 2022

Yun Sik Cho, Chang Hyun Song, Wonjun Choi, Sung Joong Kim, “NUMERICAL SIMULATION OF MELT SPREADING USING MODIFIED MOVING PARTICLE SEMI-IMPLICIT METHOD”, The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13), Taichung, Taiwan, September 4–9, 2022

Jae Hyung Park, Doyoung Shin, Taeseok Kim, Jeong Ik Lee, Yonghee Kim, Sung Joong Kim, "Lumped Analysis of Effective Coolability by Using Flooding Safety System for Small Modular Reactors", Transactions of the Korean Nuclear Society Autumn Meeting Changwon, Korea, October 21-22, 2021.

Juhyeong Lee, Taeseok Kim, Doyoung Shin, Yonghee Kim, Sangtae Kim, Sung Joong Kim, "OpenFOAM simulation of natural circulation for Passive Molten salt Fast Reactor (PMFR)", Transactions of the Korean Nuclear Society Autumn Meeting Changwon, Korea, October 21-22, 2021.

Jihun Lim, Doyoung Shin, Taeseok Kim, Jae Hyung Park, Yun Sik Cho, Yonghee Kim, Sangtae Kim, Sung Joong Kim, "Preliminary Analysis of the Effect of the Gas Injection on Natural circulation for Molten Salt Reactor Type Small Modular Reactor System Operated without a Pump", Transactions of the Korean Nuclear Society Autumn Meeting Changwon, Korea, October 21-22, 2021.

Geonhyeong Lee, Doyoung Shin, Joongoo Jeon, Taeseok Kim, Yonghee Kim, Sung Joong Kim, "CFD Assessment of Steady-State Heat Loss through Metal Containment of ATOM", Transactions of the Korean Nuclear Society Autumn Meeting Changwon, Korea, October 21-22, 2021.

Doyoung Shin, Namgook Kim, Joonyoung Bae, Sung Joong Kim, "Effects of chromium-based accident tolerant fuel coating on rewetting temperature under reflood condition," Transactions of the Korean Nuclear Society Virtual spring Meeting, May 13-14, 2021.

Joongoo Jeon, Juhyeong Lee, Sung Joong Kim, "Preliminary study of machine learning aided CFD network to reduce computational cost",  Transactions of the Korean Nuclear Society Virtual spring Meeting, May 13-14, 2021.

Taeseok Kim, Sung Joong Kim, " Condensation Performance Evaluation of Evacuate containment with Xenon, Air and CO2 for Small Modular Reactor",  Transactions of the Korean Nuclear Society Virtual spring Meeting, May 13-14, 2021.

Jihun Lim, Doyoung Shin, Taeseok Kim, Jae Hyung Park, Jeong Ik Lee, Sung Joong Kim, " Preliminary Analysis of Coupling Supercritical CO2 Cycle and Natural Draft Dry Cooling Tower for Small Modular Reactor Application", Transactions of the Korean Nuclear Society Virtual spring Meeting, May 13-14, 2021.

Doyoung Shin, Namgook Kim, Sung Joong Kim, "Experimental study of reflooding heat transfer on Cr-layered cladding under atmospheric pressure,"  Transactions of the Korean Nuclear Society Virtual Autumn Meeting, December 17-18, 2020.

Taeseok Kim, Sung Joong Kim, Jaemin Lee, Wonjoon Choi, "The dropwise condensation heat transfer characteristics of CNT/OTS layered surface associated with non-condensable gas effect,"  Transactions of the Korean Nuclear Society Virtual Autumn Meeting, December 17-18, 2020.

Joongoo Jeon, Yeon Soo Kim, Juhyeong Lee, Sung Joong Kim, "A theoretical study to compare flame characteristics of H2 and CO flames for containment safety analysis", Transactions of the Korean Nuclear Society Virtual Autumn Meeting, December 17-18, 2020.

Jihun Lim, Joongoo Jeon, Doyoung Shin, Jae Hyung Park, Sung Joong Kim, "Thermodynamic study of SCO2 Recompression Brayton Cycle with Intercooling and Reheating for Light Water Reactor", Transactions of the Korean Nuclear Society Virtual Autumn Meeting, December 17-18, 2020.

Taeseok Kim, Sung Joong Kim, "Experimental study of droplet characteristics in dropwise condensation along the axial length of a long vertical tube", Transactions of the Korean Nuclear Society Virtual Spring Meeting, July 9-10, 2020.

Doyoung Shin, Min Wook Na, Jae Hyung Park, Sung Joong Kim, "Evaluating Condenser Performance based on Pressure Transition Temperature," Transaction of the Korean Nuclear Society Autumn Meeting, Goyang, Republic of Korea, October 24-25, 2019.

Wonjun Choi, Nam Kyung Kim, Joongoo Jeon, Sung Joong Kim, "Assessment of Severe Accident Management By Multiple Mitigation Actions Using Monte Carlo Sampling", 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), Portland, OR, August, 18-23, 2019.

Joongoo Jeon, Hoichul Jung, Yeon Soo Kim, Sung Joong Kim, "Numerical study of lean limit hydrogen flames propagating upward to validate a flammability limit model", 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), Portland, OR, August, 18-23, 2019.

Namgook Kim, Hong Hyun Son, Sung Joong Kim, "Dependence of nanoscale roughness on wicking-based CHF enhancement for fresh and oxidized Cr-coated surfaces", 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), Portland, OR, August, 18-23, 2019.

Taeseok Kim, Yun Sik Cho, Sung Joong Kim, Jaemin Lee, Wonjoon Choi, "Enhancement of condensation heat transfer by hydrophobic and nano porous surface", 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), Portland, OR, August, 18-23, 2019.

Joongoo Jeon, Yeon Soo Kim, Hoichul Jung, Sung Joong Kim, "Computational study of lean limit flames in hydrogen mixtures to investigate flame propagation characteristics", Korean Nuclear Society, 2019.

Yeon Soo Kim, Joongoo Jeon, Wonjun Choi, Sung Joong Kim, "A Comparative Study of Flammability Limit Models for H2/CO mixture on the Applicability of Severe Accident Conditions", Korean Nuclear Society, 2019.

Namgook Kim, Hong Hyun Son, Sung Joong Kim, "Delayed growth of dry area with CHF enhancement on oxidized Cr-nanostructured surfaces", Korean Nuclear Society, 2019.

Jae Hyung Park, Taeseok Kim, Jong Hoon Han, Sung Joong Kim, " Effects of air injection on condensation-induced pressure shock and critical heat flux of inclined downward-facing heater", Korean Nuclear Society, 2019.

Taeseok Kim, Yun Sik Cho, Sung Joong Kim, Jaemin Lee, Wonjoon Choi, "Comparison of condensation heat transfer on hydrophobic and nano-porous surface", Transaction of the Korean Nuclear Society Autumn Meeting, Goyang, Republic of Korea, October 24-25, 2019.

Taeseok Kim, Jae Hyung Park, Jong Hoon Han, Uiju Jeong, Sung Joong Kim, "Depletion of Bubble Condensation Induced Pressure Shock
using Air injection for Core-catcher System", 9th China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-9) May 15~18, 2019 Chongqing, China

Doyoung Shin, Min Wook Na, Sung Joong Kim, Jeong Ik Lee, Yonghee Kim, "Performance of Indirect Dry Air-Cooled Condenser based on Pressure Transition Temperature for SMR Application", 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019), Juan-les-pins, France, May 12-15, 2019.

Min Wook Na, Doyoung Shin, Sung Joong Kim, Yonghee Kim, Jeong Ik Lee, "Cooling Sustainability Assessment of Passive Residual Heat Removal System Coupled with Dry Air Cooling System for SMR", 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019), Juan-les-pins, France, May 12-15, 2019.

Chang Hyun Song, Wonjun Choi, Sung Joong Kim, "Sensitivity Analysis of Corium Behavior and Properties of Concrete on Concrete Ablation during MCCI using MELCOR code", 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019), Juan-les-pins, France, May 12-15, 2019.

Joongoo Jeon, Hoichul Jung, Sung Joong Kim, "Development of CNAFT model for lower flammability of hydrogen mixtures for severe accident analysis code in nuclear power plant", 9th International Seminar on Fire and Explosion Hazards (ISFEH9), Saint-Petersburg, Russia, April 21-26, 2019

Yeon Soo Kim, Joongoo Jeon, Hoichul Jung, Sung Joong Kim, "Development and Application of Methodology to Predict the Flammability for H2/CO mixture under Severe Accident in Nuclear Power Plant", 9th International Seminar on Fire and Explosion Hazards (ISFEH9), Saint-Petersburg, Russia, April 21-26, 2019

Yun Sik Cho, Hong Hyun Son, Jong Hoon Han, Sung Joong Kim, Byung Gi Park, Ho Cheol Shin, Hwansoo Lee, "APPLICATION OF TIME-DEPENDENT GROWING MESH FOR CRUD GROWTH SIMULATION IN SINGLE ROD SCALE", 27th International Conference on Nuclear Engineering (ICONE-27), Tsukuba, Japan, May 20-22, 2019

Yun Sik Cho, Sung Joong Kim, Hwa Jeong Han, Byung Gi Park, Seungjin Seo, Sungyeol Choi, Ho Cheol Shin, Hwansoo Leed, "Prediction of CRUD Generation using Time-dependent Growing Mesh and Multi-physics Frameworks", Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia 2019 (AWC-2019), September 26-28, 2019

Doyoung Shin, Min Wook Na, Sung Joong Kim, Yonghee Kim, Jeong Ik Lee, "Efficiency Evaluation of Condenser Coupled with an Air-cooling System", 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11), Busan, Republic of Korea, Nov. 18-21, 2018.

Hong Hyun Son, Namgook Kim, Sung Joong Kim, Critical heat flux enhancement based on receding dynamics of wicked liquid varying with surface roughness, NTHAS-11, Pusan, South Korea, November 27 – 30, 2018.

Namgook Kim, Hong Hyun Son, Sung Joong Kim, "Effect of nanoscale roughness on wicking-based CHF enhancement of fresh and oxidized Cr-coated surfaces", 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11), Busan, Republic of Korea, Nov. 18-21, 2018.

Yeon Soo Kim, Wonjun Choi, Joongoo Jeon, Nam Kyung Kim, Sung Joong Kim, "Combustion Risk Analysis considering H2 and CO under SBO scenario", 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11), Busan, Republic of Korea, Nov. 18-21, 2018.

Taeseok Kim, Yun Sik Cho, Uiju Jeong, Jae Hyung Park, Sung Joong Kim, Jaemin Lee, Wonjoon Choi,, "Separate effects of wettability and wickability on pool boiling CHF", 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11), Busan, Republic of Korea, Nov. 18-21, 2018.

Yun Sik Cho, Hong Hyun Son, Byung Gi Park, Ho Cheol Shin, Hwansoo Lee, Sung Joong Kim, "Sensitivity Analysis of Thickness-based CRUD Growth Model using Separate Computing Domain", 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11), Busan, Republic of Korea, Nov. 18-21, 2018.

Min Wook Na, Doyoung Shin, Sung Joong Kim, Gwang Hyeok Seo, Jeong Ik Lee, "Feasibility Analysis of Passive Heat Removal System Coupled with Dry Air Cooling System for the ATOM System," American Nuclear Society Winter Meeting, Orlando, Florida, U.S.A, Nov. 11-15, 2018.

Joongoo Jeon, Nam Kyung Kim, Wonjun Choi, Sung Joong Kim, "Development of a Lower Flammability Limit Model for Hydrogen Risk Analysis under Severe Accident Conditions", 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Qingdao, China, October 14-18, 2018.

Taeseok Kim, Yun Sik Cho, Uiju Jeong, Jae Hyung Park, Sung Joong Kim, Jaemin Lee, Wonjoon Choi, "Nucleate Boiling Heat Transfer in Hydrophobic and Nano-porous Structured Surfaces Coated on a Vertical Tube", 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Qingdao, China, October 14-18, 2018.

Yun Sik Cho, Taeseok Kim, Uiju Jeong, Jae Hyung Park, Sung Joong Kim, "Effect of MWCNT/octadecanethiol multi-layered modification on condensation heat transfer", 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Qingdao, China, October 14-18, 2018.

Joongoo Jeon, Yeon Soo Kim, Hoichul Jung, Sung Joong Kim, "Calculated Non-Adiabatic Flame Temperature Model: Prediction of Lower Flammability Limits of Hydrogen Mixtures", Korean Nuclear Society, 2018.

Yeon Soo Kim, Joongoo Jeon, Wonjun Choi, Nam Kyung Kim, Sung Joong Kim, "Preliminary Combustion Risk Analysis of H2/CO mixture under Severe Accident using Le Chateler's Law", Korean Nuclear Society, 2018.

Hoichul Jung, Sung Joong Kim, "Calculated Non-Adiabatic Flame Temperature Model: Prediction of Lower Flammability Limits of Hydrogen Mixtures", Korean Nuclear Society, 2018.

Min Wook Na, Gwang Hyeok Seo, Doyoung Shin, Yonghee Kim, Jeong Ik Lee, Sung Joong Kim, "Feasibility Assessment of Passive Residual Heat Removal System Coupled with a Dry Air Cooling System for the ATOM System," 6th International Conference on Nuclear and Renewable Energy Resources (NURER-6), Jeju, Republic of Korea, Sep. 30 - Oct. 3, 2018.

Doyoung Shin, Min Wook Na, Yonghee Kim, Jeong Ik Lee, Sung Joong Kim, "Heat Transfer Performance of Steam Condenser Coupled with the Air-cooling System for the Small Modular Reactor," 6th International Conference on Nuclear and Renewable Energy Resources (NURER-6), Jeju, Republic of Korea, Sep. 30 - Oct. 3, 2018.

Hong Hyun Son, Yun Sik Cho., Namgook Kim, Byunggi Park, Hwansoo Lee, Ho Chul Shin, Sung Joong Kim, Review of CRUD growth models compatible with thermal-hydraulics codes for multiscale simulation, ICWCNRS, San Francisco, USA, September 9 – 14, 2018.

Doyoung Shin, Gwang Hyeok Seo, Min Wook Na, Sung Joong Kim, Yonghee Kim, Jeong Ik Lee, "Feasibility Assessment of Air-cooling System as an Ultimate Heat Sink of the ATOM System," 26th International Conference on Nuclear Engineering (ICONE-26), London, England, July 22-26, 2018.

Joongoo Jeon, Nam Kyung Kim, Wonjun Choi, Taeseok Kim, Sung Joong Kim, "Investigation of Flammability of Hydrogen Gases with Diluent Gases under Severe Accident Conditions using CNAFT Model", 26th International Conference on Nuclear Engineering (ICONE-26), London, England, July 22-26, 2018.

Wonjun Choi, Taeseok Kim, Joongoo Jeon, Nam Kyung Kim, Sung Joong , "Sensitivity Analysis of RCS Depressurization Strategy Under A Postulated SGTR Accident in OPR1000" 26th International Conference on Nuclear Engineering (ICONE-26), London, England, July 22-26, 2018.

Taeseok Kim, Wonjoon Choi, Joongoo Jeon, Nam Kyung Kim, Sung Joong , "INVESTIGATION ON FISSION PRODUCTS RELEASE MITIGATED BY IN-CONTAINMENT RELIEF VALVE UNDER SGTR ACCIDENT" 26th International Conference on Nuclear Engineering (ICONE-26), London, England, July 22-26, 2018.

Namgook Kim, Hong Hyun Son, Sung Joong Kim, "The effect of the coating and oxidation process of accident tolerant fuel cladding on the critical heat flux", Korean Institute of Metals and Materials, 2018.

Hong Hyun Son, Namgook Kim, Sung Joong Kim, "Wicking-based Enhancement of Pool Boiling Critical Heat Flux on Cr- and CrAl-coated Plate Surfaces", Korean Institute of Metals and Materials, 2018.

Uiju Jeong, Sung Joong Kim"Safety Limit Estimation of Natural Circulation Loop in EU-APR1400 Ex-vessel Core Catcher system", Korean Nuclear Society, 2018.

Doyoung Shin, Min Wook Na, Gwang Hyeok Seo, Sung Joong Kim, Yonghee Kim, Jeong Ik Lee, "Efficiency Assessment of Air-cooling System as a Final Heat Sink of the ATOM system", Korean Nuclear Society, 2018.

Gwang Hyoek Seo, Min Wook Na, Doyoung Shin, Yonghee Kim, Jeong Ik Lee, Sung Joong Kim, "Development of a Passive Residual Heat Removal System with an Air Cooling Component of the ATOM system", Korean Nuclear Society, 2018.

Uiju Jeong, Sung Joong Kim, "Understanding Role of Flow Obstacle on Bubble Behavior and CHF in Two-Phase Boundary Layer Flow", Korean Nuclear Society, 2018.

Joongoo Jeon, Wonjun Choi, Sung Joong Kim, "Development of calculated non-adiabatic flame temperature model to predict flammability limits of H2-air-diluent mixtures based on heat transfer mechanism", Korean Nuclear Society, 2018.

Yeon Soo  Kim, Nam Kyung Kim, Joongoo Jeon, Wonjun Choi, Sung Joong Kim, "Investigation of downward flow gas mixture in a PAR during SBO using the MELCOR code", Korean Nuclear Society, 2018.

Hong Hyun Son, Namgook Kim, Sung Joong Kim, "Receding behavior of wicked liquid for critical heat flux enhancement", ICBCHT, Nagasaki, Japan, March 12 - 15, 2018.

Namgook Kim, Hong Hyun Son, Sung Joong Kim, "Dependency of nanoscale particles on liquid spreading and CHF enhancment", ICBCHT, Nagasaki, Japan, March 12 - 15, 2018.

Joongoo Jeon, Wonjun Choi, Sung Joong Kim, "Improved Safety Injection Flow Map Associated with Target RCS Depressurization to Maintain Core Coolability of OPR1000", American Nuclear Society, 2017.

Hong Hyun Son, Gwang Hyeok Seo, Uiju Jeong, Sung Joong Kim, "Enhanced pool boiling critical heat flux with Cr-sputtered superhydrophilic metal surface", ICAPP, 2017.

Nam Kyung Kim, Joongoo Jeon, Wonjun Choi, Sung Joong Kim, "Benchmarking study of THAI-HD Experiments by Adjusting Combustion Model in MELCOR Code", NURETH-17, 2017.

Gwang Hyoek Seo, Doyoung Shin, Honghyun Son, Sung Joong Kim, "PIV Investigation of Natural Convective Flow inside 8×8 Partial Fuel Assembly", NURETH-17, 2017.

Doyoung Shin, Uiju Jeong, Jae Sung Kwon, Sung Joong Kim, "PIV Investigation of Natural Convective Flow inside 8×8 Partial Fuel Assembly", NURETH-17, 2017.

Hong Hyun Son, Yun Sik Cho, Sung Joong Kim, "Comparative Study of Boiling Heat Transfer Between FeCrAl- and Cr-Layered Vertical Tubes in Saturated Pool Boiling", NURETH-17, 2017.

Wonjun Choi, Nam Kyung Kim, Joongoo Jeon, Sung Joong Kim, "Investigation of severe accident management by multiple mitigation actions under SGTR accident", NURETH-17, 2017.

Gwang Hyeok Seo, Doyoung Shin, Honghyun Son, Sung Joong Kim, "Preliminary Study of Conceptual Design of the ATOM Safety System", Korean Nuclear Society, 2017.

Joongoo Jeon, Wonjun Choi, Nam Kyung Kim, Yongjae Lee, Sung Joong Kim, "Improved Safety Injection Flow Model Associated with Target Depressurization during Severe Accident Management", Korean Nuclear Society, 2017.

Uiju Jeong, Yeon Soo Kim, Taeseok Kim, Nam Kyung Kim, Sung Joong Kim, "Analysis of the Mechanistic Critical Heat Flux Models for Downward Facing Boiling Heat transfer", Korean Nuclear Society, 2017.

Gwang Hyoek Seo, Minwook Na, Doyoung Shin, Hong Hyun Son, Yonghee Kim, Jeong Ik Lee, Sung Joong Kim, "Development of Conceptual Design for the ATOM Safety System", Korean Nuclear Society, 2017.

Uiju Jeong, Yeon Soo Kim, Taeseok Kim, Nam Kyung Kim, Sung Joong Kim, "Preliminary Study of Conceptual Design of the ATOM Safety System", Korean Nuclear Society, 2017.

Nam Kyung Kim, Joongoo Jeon, Wonjun Choi, Kyusang Song, Gyoodong Jeun, Sung Joong Kim, "Investigation of hydrogen risk in the major containment compartments of OPR1000 using MELCOR code under SBO scenario", Korean Nuclear Society, 2017.

Doyoung Shin, Uiju Jeong, Sung Joong Kim, "PIV Investigation on the Natural Convective Flow inside 8×8 Spent Fuel Assembly", Korean Nuclear Society, 2017.

Wonjun Choi, Joongoo Jeon, Nam Kyung Kim, Sung Joong Kim, "MELCOR assessment of sequential severe accident mitigation actions under SGTR accident", Korean Nuclear Society, 2017.

Honghyun Son, Yun Sik Cho, Sung Joong Kim, "Dynamic wetting characteristics attributable for pool boiling heat transfer of FeCrAl- and Cr-layered vertical tubes", Korean Nuclear Society, 2017.

Namgook Kim, Hong Hyun Son, Sung Joong Kim, "Dynamic wetting behavior on oxidized surfaces and its effect on pool boiling critical heat flux", Korean Nuclear Society, 2017.

Namgook Kim, Hong Hyun Son, Sung Joong Kim, "Monotonic CHF increase with enhanced wicked liquid volume rate on nanostructured surfaces", Korean Nuclear Society, 2017.

Yun Sik Cho, Hong Hyun Son, Sung Joong Kim, "Effect of surface wettability and roughness on pool boiling heat transfer of Cr-layered vertical tube.", Korean Nuclear Society, 2017.

Taeseok Kim, Jaemin Lee, Wonjoon Choi, Uiju Jeong, Gwang Hyeok Seo, Hong Hyun Son, Sung Joong Kim, "Enhanced critical heat flux in the downward facing pool boiling using layer-by-layer assembled carbon nanotube", Transaction of the Korean Nuclear Society Spring Meeting, Jeju, Republic of Korea, 2017.

Joongoo Jeon, Doyoung Shin, Wonjun Choi, Nam Kyung Kim, Gyoodong Jeun, Sung Joong Kim, "Mitigation of Local Hydrogen Combustion by Inertization during Pressurizer Surgeline Failure Induced SBO Accident", NUTHOS-11, 2016.

Wonjun Choi, Nam Kyung Kim, Joongoo Jeon, Gyoodong Jeun, Sung Joong Kim, "Overall effectiveness of multiple actions of severe accident mitigation strategies of OPR1000 under SBLOCA, SBO, and TLOFW scenarios", NUTHOS-11, 2016.

Uiju Jeong, Kyusang Song, Honghyun Son, Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "An experimental investigation of downward facing critical heat flux in a rectangular channel with the aligned flow obstacles", NUTHOS-11, 2016.

Nam Kyung Kim, Joongoo Jeon, Wonjun Choi, Gyoodong Jeun, Sung Joong Kim, "Capturing Local Hydrogen Risk in the OPR1000 Containment using MELCOR Simulation under SBO Scenario", NUTHOS-11, 2016.

Doyoung Shin, Uiju Jeong, Gyoodong Jeun, Sung Joong Kim, "CFD Analysis of Passive Heat Removal by Various Gases in the Spent Fuel Dry Storage System", NUTHOS-11, 2016.

Gwang Hyeok Seo, Uiju Jeong, Honghyun Son, Gyoodong Jeun, Sung Joong Kim, "Effect of CNT layer on pool boiling critical heat flux using Layer-by-Layer assembly technique", NUTHOS-11, 2016.

Wonjun Choi, Yongjae Lee, Sung Joong Kim, "Thermal-Hydraulic Analysis of PHWR Containment using MELCOR Code", NUTHOS-11, 2016.

Joongoo Jeon, Nam Kyung Kim, Gyoodong Jeun, Sung Joong Kim, Yong-Jin Cho, "Assessment of THAI HD Tests by Adjusting MELCOR 2.1 Model", NTHAS10, 2016.

Gwang Hyeok Seo, Honghyun Son, Gyoodong Jeun, Sung Joong Kim, "Effects of a FeCrAl layer fabricated by sputtering process on pool boiling critical heat flux", NTHAS10, 2016.

Uiju Jeong, Nam Kyung Kim, Hong Hyun Son, Gyoodong Jeun, Sung Joong Kim, "Effect of the aligned obstacles on subcooled flow boiling in downward inclined rectangular channel", NTHAS10, 2016.

Uiju Jeong, Honghyun Son, Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "Effect of the Aligned Flow Obstacles on Downward-Facing CHF in an Inclined Rectangular Channel", Korean Nuclear Society, 2016.

Kyusang Song, Wonjun Choi, Nam Kyung Kim, Joongoo Jeon, Gyoodong Jeun, Sung Joong Kim, "MELCOR Simulation of Effects of Cavity Flooding Strategy on the RPV Failure and Containment Leak for OPR1000", Korean Nuclear Society, 2016.

Honghyun Son, Uiju Jeong, Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "Neutralized wettability effect of superhydrophilic Cr-layered surface on pool boiling critical heat flux", Korean Nuclear Society, 2016.

Joongoo Jeon, Wonjun Choi, Nam Kyung Kim, Gyoodong Jeun, Sung Joong Kim, "MELCOR Simulation of Containment Spray for Potential Regulation of 100TBq Cesium-137 Release from OPR1000", Korean Nuclear Society, 2016.

Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "FeCrAl Layer Fabricated by DC Sputtering Enhances Pool Boiling Critical Heat Flux", Korean Nuclear Society, 2016.

Gwang Hyeok Seo, Uiju Jeong, Honghyun Son, Gyoodong Jeun, Sung Joong Kim, "Development of Surface Modification Techniques for Enhanced Safety of Light Water Reactors: Recent Progress and Future Direction at THLAB", Korean Nuclear Society, 2016.

Nam Kyung Kim, Joongoo Jeon, Wonjun Choi, Kyusang Song, Gyoodong Jeun, Sung Joong Kim, "Investigation of Local Hydrogen Risk in the RDT Compartment of OPR1000 under SBO Scenario", Korean Nuclear Society, 2016.

Doyoung Shin, Uiju Jeong, Sung Joong Kim, "CFD Analysis on the Passive Heat Removal by Helium and Air in the Canister of Spent Fuel Dry Storage System", Korean Nuclear Society, 2016.

Seongnyeon Lee, Jung-Jae Lee, Sung Joong Kim, Se Hong Oh, Cheongryul Choi, Yong-Jin Cho, "Evaluation of Hydrogen Distribution against THAI HM-2 Experiment using MELCOR and CFX", 2015.

Yongjae Lee, Seungwon Seo, Hwan-Yeol Kim, Sung Joong Kim, "Analysis of Onset of Oxidation during Hypothesized Severe Accidents of Korean Optimized Power Reactor 1000", ICAPP, 2015.

Honghyun Son, Uiju Jeong, Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "Effect of Wettability and Capillary Wicking Changes Induced by Oxidation on the Pool Boiling Critical Heat Flux", ICAPP, 2015.

Honghyun Son, Uiju Jeong, Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "Effect of oxide layer thickness on the pool boiling critical heat flux of pre-oxidized RPV material", NURETH-16, 2015.

Gwang Hyeok Seo, Honghyun Son, Uiju Jeong, Gyoodong Jeun, Sung Joong Kim, "Effects of various thin film coating techniques on pool boiling heat transfer", NURETH-16, 2015.

Yongjae Lee, Wonjun Choi, Sungchu Song, Namduk Suh, Seon Oh Yu, Sung Joong Kim, "Preliminary Evaluation of Hydrogen Risk for Pressurized Heavy Water Reactor Using MELCOR Code", WORTH-7, 2015.

Wonjun Choi, Yongjae Lee, Hwan-Yeol Kim, Rae-Joon Park, Sung Joong Kim, "Severe Accident Analysis of Steam Generator Tube Rupture Postulated for the OPR1000 using MELCOR", WORTH-7, 2015.

Kyusang Song, Honghyun Son, Uiju Jeong, Sung Joong Kim, "Thermal-Hydraulic Effects of Stud Shape and Size on the Safety Margin of Core Catcher System", Korean Nuclear Society, 2015.

Wonjun Choi, Yongjae Lee, Sung Joong Kim, Hwan-Yeol Kim, Rae-Joon Park, "Effect of In-Vessel Retention Strategies under Postulated SGTR Accidents of OPR1000", Korean Nuclear Society, 2015.

Kyusang Song, Honghyun Son, Uiju Jeong, Doyoung Shin, Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "Experimental Study for Effects of the Stud shape of the Core Catcher System", Korean Nuclear Society, 2015.

Wonjun Choi, Yongjae Lee, Sung Joong Kim, Hwan-Yeol Kim, "Effectiveness of Modified Jakob Number as a SAMG Entry Condition", Korean Nuclear Society, 2015.

Gwang Hyeok Seo, Honghyun Son, Uiju Jeong, Gyoodong Jeun, Sung Joong Kim, "Pool Boiling Heat Transfer Characteristics of Chromium Coatings Deposited by RF Magnetron Sputtering", Korean Nuclear Society, 2015.

Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "Superior Thermal Performance of SiC Cladding under Extreme Pool Boiling Conditions", American Nuclear Society, 2014.

Gwang Hyeok Seo, Jongwoong Yoon, Sung Joong Kim, Hayoung Hwang, Taehan Yeo, Woonjoon Choi, "Enhanced Pool Boiling Critical Heat Flux of Water Using Carbon Nanotubes Adhesion on Stainless Steel Heaters", American Nuclear Society, 2014.

Yongjae Lee, Seungwon Seo, Sung Joong Kim, Kwang Soon Ha, Hwan-Yeol Kim, "Reactor Core Coolability Analysis during Hypothesized Severe Accidents of OPR1000", Korean Nuclear Society, 2014.

Honghyun Son, Uiju Jeong, Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "Oxidation Effect on Pool Boiling Heat Transfer in Atmospheric Saturated Water", Korean Nuclear Society, 2014.

Seungwon Seo, Gyoodong Jeun, Sung Joong Kim, Hwan-Yeol Kim, Kwang Soon Ha, "The Effect of the SIT Injection Rate on Delaying RPV Failure during Severe Accidents", Korean Nuclear Society, 2014.

Uiju Jeong, Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "A Preliminary Study of the Core Catcher System on Various Stud Shapes using FLUENT", Korean Nuclear Society, 2014.

Junkyu Han, Yongjae Lee, Sung Joong Kim, "High-Speed Detection of Onset of Nucleate Boiling of DI Water at Stainless Steel Heater Confined in Narrow Rectangular Vertical Channel", Korean Nuclear Society, 2014.

Yongjae Lee, Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "Preliminary Numerical Analysis of Convective Heat Transfer Loop Using MARS Code", Korean Nuclear Society, 2014.

Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, "Pool Boiling Behavior and Critical Heat Flux on Zircaloy and SiC Claddings in Deionized Water under Atmospheric Pressure", Korean Nuclear Society, 2014.

Sung Joong Kim, “Thermal-Hydraulic Analysis for HEU and LEU Transitional Core Conversion of the MIT Research Reactor”, American Nuclear Society, 2013.

Gwanghyeok Seo, Sung Joong Kim, “Experimental Study of Pool Boiling Heat Transfer and Critical Heat Flux on a Horizontal Zircaloy Tube”, KNS Spring proceeding, 2013.

Uiju Jeong, Yoonho Kim, Sung Joong Kim, “CFD Analysis of Liquid Sodium Flow in the Vicinity of Permanent Magnet Probe Flow Meter using FLUENT”, ANS 2013 Student conference, 2013.

Junkyu Han, Gwanghyeok Seo, Honghyun Son, Sung Joong Kim, “Determination of Onset of Nucleate Boiling in a Vertical Rectangular Channel at Atmospheric Pressure Rates” WORTH-6, 2013.

Gwanghyeok Seo, Youngho Kim, Sung Joong Kim, “LBLOCA Analysis of OPR1000 with Deployment of Severe Accident Tolerable SiC Fuel Cladding”, ICAPP, 2013.

Honghyun Son, Gwanghyeok Seo, Sung Joong Kim, “MARS Code Assessment of Main Steam Line Break accident in ATLAS”, KNS Spring proceeding, 2013.

Seungwon Seo, Sung Joong Kim, “MELCOR Simulation of Direct Depressurization Strategy for Total Loss of Feed Water Accident”, KNS Spring proceeding, 2013.

 Junkyu Han, Youngho Kim, Sung Joong Kim, “Visualization of Onset of Nucleate Boiling in a Narrow Rectangular Channel at Low Pressure”, Paper ICMF2013-345, International Conference on Multiphase Flow 2013, Jeju, Korea, May 26-31, 2013.

Gwang Hyeok Seo, Junkyu Han, Gyoodong Jeun, Sung Joong Kim, “Pool Boiling Heat Transfer Characteristics of Severe Accident Tolerable SiC Fuel Cladding”, Paper ICMF2013-344, International Conference on Multiphase Flow 2013, Jeju, Korea, May 26-31, 2013.

Gwang Hyeok Seo, Junkyu Han, Gyoodong Jeun, Sung Joong Kim, “Experimental Study of Boiling Heat Transfer of Steam Oxidized Zircaloy Tube”, Paper ####, 2013 International Congress on Advances in Nuclear Power Plants, Jeju, Korea, April 14-18, 2013.

Youngho Kim, Seongnyeon Lee, Gwang Hyeok Seo, Sung Joong Kim, “Computational LOCA Analysis of OPR1000 with Severe Accident Tolerable SiC Fuel Cladding”, Paper ####, 2013 International Congress on Advances in Nuclear Power Plants, Jeju, Korea, April 14-18, 2013.

Seongnyeon Lee, Gwang Hyeok Seo, Sung Joong Kim, “Computational Analysis of Grid Effect of RBHT Experiment Using MARS-KS and FLUENT”, Paper Number N8P1092, The Eighth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, Beppu, Japan, December 9-12, 2012.

Yoonho Kim, Ui Ju Jeong, Sung Joong Kim, “State-of-the-art Measurement Techniques for Thermal Parameters of Liquid Metal Flow”, Paper Number N8P1025, The Eighth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, Beppu, Japan, December 9-12, 2012.

Gwang Hyeok Seo, Seongnyeon Lee, Gyoodong Jeun, Sung Joong Kim, “Effect of Oxidation on the Wettability Change with Metal Surfaces”, Transactions of the Korean Nuclear Society Autumn Meeting, Gyeongju, Korea, October 25-26, 2012.

Uiju Jeong, Yoon Ho Kim, Sung Joong Kim, “Computational Analysis of Distorted Velocity and Temperature Profiles of Sodium Flow in the Vicinity of Local Velocity Probe”, Transactions of the Korean Nuclear Society Autumn Meeting, Gyeongju, Korea, October 25-26, 2012.

Seongnyeon Lee, Hwan-Yeol Kim, Jong-Hwa Park, Sung Joong Kim, “MELCOR Simulation of Postulated Severe Accidents in OPR1000”, Transactions of the Korean Nuclear Society Autumn Meeting, Gyeongju, Korea, October 25-26, 2012.

Sung Joong Kim, D. Carpenter, G. Kohse, K. Terrani, L. W. Hu, “Thermal-Hydraulic Analysis of LWR Hydride Fuel Irradiation Experiment in MITR”, American Nuclear Society 2012 Annual Meeting, Embedded Topical Meeting: NFSM, Chicago, Illinois, USA, June 24-28, 2012.

Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, “A State-of-the-art of Wettability Effect on Boiling Heat Transfer Enhancement”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 17-18, 2012.

Seongnyeon Lee, Gwang Hyeok Seo, Sung Joong Kim, “Severe Accident Analysis of OPR1000 Postulating SBO and SBLOCA Using MELCOR”, Paper 187, 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics, Pisa, Italy, May 12-16, 2012.

Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim, “MARS Assessment of RBHT Experimental Data for Various Pressures and Flooding Rates”, Paper 308, 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics, Pisa, Italy, May 12-16, 2012.

Uiju Jeong, Yun Ho Kim, Sung Joong Kim, “Experimental and Computational Investigation on Thermal Flow Measurement of Liquid Sodium in the ITSL”, Paper 311, 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics, Pisa, Italy, May 12-16, 2012.

Sung Joong Kim, Y. C. Ko, L. W. Hu, “Loss of Flow Accident Analysis of the MIT Research Reactor HEU-LEU Transitional Cores Using RELAP5-3D”, Paper 10224, Proceedings of ICAPP 2010, San Diego, CA, June 13-17, 2010.

B. Truong, L. W. Hu, J. Buongiorno, T. McKrell, Sung Joong Kim, “Subcooled Flow Boiling Critical Heat Flux Enhancement of Alumina Nanoparticle Pre-coated Tubing”, ECI International Conference on Boiling Heat Transfer, Florianópolis-SC-Brazil, May 3-7, 2009.

Sung Joong Kim, T. McKrell, J. Buongiorno, L. W. Hu, “Subcooled Flow Boiling Heat Transfer of Dilute Alumina, Zinc Oxide, and Diamond Nanofluids at Atmospheric Pressure”, Paper 032, The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7), Seoul, Korea, October 5-9, 2008.

Sung Joong Kim, T. McKrell, J. Buongiorno, L. W. Hu, “Experimental Study of Flow Critical Heat Flux in Low-Concentration Water-Based Nanofluids”, Paper 52321, Proceedings of Micro/Nanoscale Heat Transfer International Conference (MNHT2008), Tainan, Taiwan, January 6-9, 2008.

Sung Joong Kim, T. McKrell, J. Buongiorno, L. W. Hu, “Enhancement of Flow Critical Heat Flux in Water-Based Nanofluids with Alumina Nanoparticles”, Paper B00005, Proceedings of the 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-12), Pittsburgh, September 30-October 4, 2007.

Sung Joong Kim, B. Truong, J. Buongiorno, L. W. Hu, I. C. Bang, “Study of Two-phase Heat Transfer in Nanofluids for Nuclear Applications”, Paper 6005, Proceedings of ICAPP ’06, Reno, NV, USA, June 4-8, 2006. -

Yong H. Kim, Sung Joong Kim, Sang W. Noh, Kune Y. Suh, “Critical Heat Flux in One-Dimensional Downward-Heated Channel,” American Nuclear Society Annual Meeting, San Diego, CA, USA, June 1-5, 2003.

Sang W. Noh, Yong H. Kim, Sung Joong Kim, Kune Y. Suh, Joy L. Rempe, Fan B. Cheung, Sang B. Kim, “An Experimental Study of in Inclined One-Dimensional Channels,” The 10th International Topic Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9, 2003.

Sung Joong Kim, Yong H. Kim, Sang W. Noh, Kune Y. Suh, Joy L. Rempe, Fan B. Cheung, Sang B. Kim, “Experimental Study of Critical Heat Flux in Inclined Rectangular Gap,” International Conference on Global Environment and Advanced Nuclear Power Plants, Kyoto, Japan, September 15-19, 2003.

Yong H. Kim, Sung Joong Kim, Sang W. Noh, Kune Y. Suh, “Critical Heat Flux in Narrow Gap in Two-Dimensional Slices under Uniform Heating Condition,” The 17th International Conference on Structural Mechanics in Reactor Technology, Prague, Czech Republic, August 17-22, 2003.

Yong H. Kim, Sang W. Noh, Sung Joong Kim, Kune Y. Suh, “Azimuthal Critical Heat Flux in Narrow Rectangular Channels,” Proceedings of the Korean Nuclear Society Spring Meeting, Gyeongju, Korea, May 29-30, 2003.

Sung Joong Kim, Yong H. Kim, Kune Y. Suh, Joy L. Rempe, Fan B. Cheung, Sang B. Kim, “One-Dimensional Downward-Facing Critical Heat Flux Concerning Surface Orientation and Gap Size Effects,” International Congress on Advances in Nuclear Power Plants, Cordoba, Spain, May 4-7, 2003.

Yong H. Kim, Sung Joong Kim, Sang W. Noh, Kune Y. Suh, “Measurement of Critical Heat Flux in Narrow Gap with Two-Dimensional Slices,” Proceedings of the Korean Nuclear Society Spring Meeting, Kwangju, Korea, May 23-24, 2002.

Yong H. Kim, Sung Joong Kim, Sang W. Noh, Kune Y. Suh, “The Critical Heat Flux in Narrow Gap with Two-Dimensional Slice Geometry for Uniform Heating Method,” Third Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, Gyeongju, Korea, October 13-16, 2002.