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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2026-Autumn 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 11:20 300B Evaluation of Off-Design Safety Margins for the Nuclear Power Plant ESW-CCW Cooling System under Rising Seawater Temperatures Using Flowmaster Joohyung Jung, Taejun Song, and Seongmin Son(Kyungpook National Univ.) PDF보기 -
2026-Autumn 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 11:40 300B Preliminary Study of Xe-135 Reactivity Transient Analysis in a Natural-Circulation Molten Salt Reactor Using a GAMMA+ Coupled Mass Transport Model WonJun Choi and SungJoong Kim(HYU), Lin-wen Hu(MIT) PDF보기 -
2026-Autumn 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 12:00 300B Development of Nusselt Number and Darcy Friction Factor Correlations for a NACA 0020 Airfoil PCHE Using MgCl₂-KCl Molten Salt Dogyun Kim, Taewoo Kim, and Sang Ji Kim(KAERI) PDF보기 -
2026-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 13:30 203 Transient Drainage Performance of a Marine Molten Salt Reactor under Rolling Motion Hyeon Ji Kim and In Cheol Bang(UNIST) PDF보기 -
2026-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 13:50 203 Preliminary Numerical Analysis of Freeze Valve Opening Time with Consideration of Salt Plug Solidification in a Molten Salt Reactor Joo Hyung Seo and In Cheol Bang(UNIST) PDF보기 -
2026-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 14:10 203 Feasibility Test of Hydrodynamic-driven Salt Drain System for Cartridge-Type Molten Salt Reactor Seolhui Kim, Ik Jae Jin, and In Cheol Bang(UNIST), Doyeong Lim(CSU), Ji Yong Kim(JBNU) PDF보기 -
2026-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 14:50 203 GPU-Accelerated 3D Simulation of Molten Salt Spreading Using Moving Particle Method Wiktor Gronek and Han-Young Yoon(KINGS) PDF보기 -
2026-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 15:10 203 Development of a Size-Resolved Noble Metal Transport Code for a Passive Molten Salt Fast Reactor and Its Coupling with Serpent Depletion Calculations Yun Sik Cho and Sung Joong Kim(HYU), Inyup Kim and Yonghee Kim(KAIST) PDF보기 -
2026-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 15:30 203 Analysis of Six-Degree-of-Freedom Motion Effects on Sodium Pool Behavior in a Marine SFR Reactor Vessel Using AMESim SEONGON KIM, SANGBUM SON, and JAE-HO JEONG(CAU) PDF보기 -
2026-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 09:00 300C Development of OpenFOAM VOF Solver with Interfacial Mass-Transfer and Variable Properties for Heat Pipe CFD Simulations Almanzo Arjuna and In Cheol Bang(UNIST) PDF보기 -
2026-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 09:20 300C A Coupled OpenFOAM–DEM Framework for Solid–Fluid Multiphase Flow Simulation Jeong Woo Choi, Eun Sung Kim, and Young Beom Jo(KHU) PDF보기 -
2026-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 09:40 300C Transient VOF Simulation of Air-Water Two-Phase Flow in Helically Coiled Tubes under Various Flow Regimes Sangoh Shin, Janghun Han, and Minseop Song(HYU), Yujeong Ko, Byeongil You, and Hyoungkyu Cho(SNU) PDF보기 -
2026-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 10:00 300C Single-Phase Flow and Heat Transfer Analysis of a Helical Coil Tube Using CUPID Michal Henryk Wroblewski and Han-young Yoon(KINGS) PDF보기 -
2026-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 10:20 300C A Methodology for Deriving a Heat Trasfer Correlation for a Supercritical CO2, Precooler Using a Segment-Based Model and Trust-Region Reflective Optimization JuWon Jung, JaeEun Cha, and Gibbeum Lee(KAERI) PDF보기 -
2026-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 11:00 300C Effect of Main Compressor Design on the Off-Desgin Operation Range of sCO2 Recompression Cycle Chanyong Park and Jeong Ik Lee(KAIST) PDF보기 -
Last Modified : 1998-Autumn