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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 14:10 301 (3F) High-fidelity Numerical Investigation on Structural Integrity for SFR Fuel Cladding during Design Basis Events SeoYoon Choi and JaeHo Jeong(Gachon Univ.), HyungKyu Kim(KAERI) PDF보기 -
2023-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 14:30 301 (3F) Analysis of a CEA Ejection Scenario for the Korean APR1400 Reactor using BEPU Approach Ditsietsi Malale, Saja Rababah, Sebastian Dzien, and Aya Diab(KINGS) PDF보기 -
2023-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 14:50 301 (3F) System Code Analysis of MSGTR Mitigation with Passive Auxiliary Feedwater System Seongsu Jeon, Youngjae Park, Jaeho Bae, Jungjin Bang, and Youngwook Chung(FNC Tech.), Dohyun Hwang(KHNP) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 09:00 301 (3F) Analysis of Natural Circulation Characteristics of Passive Molten Salt Fast Reactor by using OpenFOAM Simulation Juhyeong Lee, Sangtae Kim, and Sung Joong Kim(HYU), Yonghee Kim(KAIST) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 09:20 301 (3F) Selecting Optimal Heat Transfer Chloride Salt for Molten Salt Fast Reactor Sungwook Choi, Taeyoen Min, In Woo Son, Sunghyun Yoo, and Jeong Ik Lee(KAIST) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 09:40 301 (3F) Assessment of Helium Bubbling Effect on Natural Circulation Applicable for Passive Molten Salt Fast Reactor Wonjun Choi, Jae Hyung Park, Juhyeong Lee, Jihun Lim, Yunsik Cho, Sangtae Kim, and Sung Joong Kim(HYU), Yonghee Kim(KAIST), Youngsoo Yoon(Gachon Univ.) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 10:00 301 (3F) Investigation of Computational Dynamic Modeling of Helical Once-Through Steam Generator for Integrated System Analysis Keon Yeop Kim, Youngsuk Bang, So Eun Shin, Haneul Na, and Yeon Jun Choo(FNC Tech.) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 10:20 301 (3F) CFD Study of Two-phase Flow Pressure Drop in Helical Tube Steam Generator Doh Hyeon Kim, Seunghwan Oh, and Jeong Ik Lee(KAIST) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 11:00 301 (3F) Influence of Coil Thickness on Natural Convection Heat Transfer of Helical Coil Dong Ho Shin and Bum Jin Chung(KHU) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 11:20 301 (3F) Experimental Design Procedure for Tubes in Turbulent Cross Flow Dong Seok Oh, Heung Seok Kang, Kang Hee Lee, Chan Lee, and Soo Ho Kim(KAERI) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 11:40 301 (3F) Effect of Exit Restriction on the Two-phase Natural Circulation Flow as PCCS Sun Taek Lim, Koung Moon Kim, and Ho Seon Ahn(INU), Dong-Wook Jerng(CAU) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 12:00 301 (3F) The Conceptual Heat Exchanger Design for Heat Pipe Cooled Micro Reactor Faruk Celik and In Cheol Bang(UNIST) PDF보기 PPT보기
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Thermal-Hydraulic and Thermo-Mechanical Behavior Under Nitrogen Inflow Condition in a Large Break Loss of Coolant Accident Jae Bong Lee, Jongrok Kim, Kihwan Kim, Sang-Ki Moon, and Seok Kim(KAERI) PDF보기 -
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Test Requirements for Surface Characteristics of High Burnup Cladding Under LOCA and RIA Conditions S. K. Moon, J. Kim, Y. S. Choi, K. Kim, J. B. Lee, B. G. Jeon, and S. Kim(KAERI) PDF보기 -
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Design Guide for Water Heat Pipes for Nuclear Power Plant Applications Based on the Thermal Limit Evaluation Ye Yeong Park and In Cheol Bang(UNIST) PDF보기 -
Last Modified : 1998-Autumn