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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Validation of Two-Phase Flow Boiling Heat Transfer Correlations and Application to Steam Generator Design Hyochan Kim, Jun Ha Hwang, Doh Hyeon Kim, and Jeong Ik Lee(KAIST) PDF보기 -
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Preliminary Study on Working Fluids for Power Conversion in Space Heat Pipe Reactors Seunghwan Oh, Hong-sik Lim, Sung Nam Lee, Nam-il Tak, and Chan Soo Kim(KAERI) PDF보기 -
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Influence of Tube Design and Analytical Parameters on Steam Generator Tube Behavior in One-way FSI Analysis Dae Kyung Choi, Choengryul Choi, Won Man Park, Young Min Byun, and SeungMok Yoo(Elsoltec), YoungJin Oh, Heejae Shin, and Sang Hoon Lee(KEPCO E&C) PDF보기 -
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Sensitivity Analysis According to the Break Loop Location in the MSGTR Accident BUMSOO YOUN and CHANGKEUN YANG(KHNP), BOGAM YOUN(KEPCO E&C) PDF보기 -
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Net Efficiency–Equipment Trade-offs in PWR-SMR Rankine Cycles: Impacts of Steam-Generator Pressure and Temperature Gyudong Kim and Jeong Ik Lee(KAIST) PDF보기 -
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Assessment of Flow Boiling Heat Transfer Prediction Capability of MARS-KS in Helical Coil Tube Seongman Jeong and Taewan Kim(Incheon National Univ.) PDF보기 -
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Preliminary Validation of Thermal-Hydraulic Module for Ex-vessel Severe Accident Analysis through Containment Experiments KumHo Han, JeHee Lee, and Yeon-Jun Choo(FNC Tech.) PDF보기 -
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I CUPID-PRAGMA Coupling Method using preCICE library Seongju Do(KAERI) PDF보기 -
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I A New Form Loss Coefficient Model in CAP for Long Term Containment Vessel Air Cooling Analysis Minseok Choi, Kum-Ho Han, Bub-Dong Chung, and Soon-Joon Hong(FNC Tech.) PDF보기 -
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Effect of Hybrid-Overlap Contact Modeling on Porosity and Pressure Drop in Pebble Bed Reactor CFD Analysis Seongmin Hong and Minseop Song(HYU) PDF보기 -
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I A Reduced-Order Multi-Variable Surrogate Approach for Cross Flow Dynamics in Helical Coil Steam Generators Using POD and LSTM Bumjin Cho and Minseop Song(HYU) PDF보기 -
2025-Autumn 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Preliminary CFD Study on Free Jet Flow at the Marviken Test Facility Gong Hee Lee and Seon Ho Choi(KINS) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Xenon Reactivity Model Integrated with Point Kinetics of the SPACE Code Seung Wook LEE, Kwi Seok HA, and Jong Hyuk LEE(KAERI) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I The Development of Phenomena Identification and Ranking Table for Innovative Small Modular Reactor Yerim Park, MinJeong Kim and Dong-Hyuk Lee(KHNP) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Study on the Effect of Heat Removal Ratio of PAFS and PCCS on Core Level in i-SMR Using Simplified Model Dong-Hyuk Lee and Yerim Park(KHNP) PDF보기 -
Last Modified : 1998-Autumn