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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby A High-Fidelity Multiphysics Analysis Method for the MSFR Reactor Using CUPID–PRAGMA Coupling Seongju Do and Jaeuk Im(KAERI) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Development of a SPH-DOM Solver for Radiative Heat Transfer with Complex Geometry Hoon Chae and Eung Soo Kim(SNU) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby SST-IDDES Analysis of Vane-Induced Unsteady Mixing in a 4×4 Rod Bundle with Split-Type Mixing Vanes Chaehyeon Song and Minseop Song(HYU) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Preliminary Performance Comparison of CNN and GNN Based Reduced-Order Models for Large-Scale CFD Simulations Seongmin Oh(JBNU), Minseo Lee and Joongoo Jeon(POSTECH), Minseop Song, Bumjin Cho, and Chaehyeon Song(HYU) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Preliminary Numerical Simulation of Fluid Flow in a Helical Coil Steam Generator: A comparative study of LBM and FVM Junyong Park(JBNU), Minseo Lee and Joongoo Jeon(POSTECH), Bumjin Cho, and Chaehyeon Song, Minseop Song(HYU) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Integral Effect Test Based Validation of the Passive Auxiliary Feedwater System (PAFS) Condensation Model in the SPACE Code Jong-Hyuk Lee, Hae-Min Park, and Sung-Won Bae(KAERI) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Preliminary Evaluation of Structural Effect on Extended-term Cooling Capability of On-demand Flooding System Using MARS-KS Jae Hyung Park, Jihun Im, Hyo Jun An, and Sung Joong Kim(HYU) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Energy Supply Strategy for an AI Data Center by Integrating SMR with Multi Turbine Cooling System Using Joule-Thomson Expansion Tae Yang Lee, Yeong Chan Kim, and Jeong Ik Lee(KAIST) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Evaluation of CHF Correlation Model Performance in MATRA for Various Rod Bundle Geometries Seojun Park and Kyung Mo Kim(KENTECH) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Hydrodynamic Feasibility Test of Gravity-Driven Drainage in Cartridge-Type Molten Salt Reactor Seolhui Kim, Ik Jae Jin, Doyeong Lim, and In Cheol Bang(UNIST) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby sCO2 Brayton Cycle Layout Study on Gas-cooled Reactor for Maritime Propulsion Chanyong Park and Jeong Ik Lee(KAIST) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Preliminary Analysis of SBLOCA Test for SMART-ITL using the SPACE Code Yongjae Lee, Hwang Bae, and Jong-Hyuk Lee(KAERI) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Comparative Assessment of Boiling Heat Transfer Predictability of System Codes MARS-KS and TRACE in Helically Coiled Tubes Seongman Jeong, Yunseok Lee, and Taewan Kim(INU) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Numerical Validation of Molten Salt Spill and Solidification Behaviors using ANSYS Fluent and OpenFOAM Ye Hwan Chun, Juhyeong Lee, JinHo Song, and Sung Joong Kim(HYU) PDF보기 -
2026-Spring 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:00 Lobby Assessment of the Heat Transfer Model of a Helically Coiled Tube in MARS-KS and SPACE Codes Tae Wook Ha and Jong-Hyuk Lee(KAERI) PDF보기 -
Last Modified : 1998-Autumn