학술정보출판물

한국원자력학회에 오신 것을 환영합니다.

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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 -
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Hydraulic and Thermal Behaviors of Diabatic Two-phase Flow Through Porous Particle Beds Lee Dong Ju, Oh Jong Seok, and Kim Dong Eok(CAU), An Sang Mo and Kim Hwan Yeol(KAERI) PDF보기 -
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Experimental Study on Performance of Pitot-Static Tube with Varying Pitch Angles Byungjun Lim, Kihwan Kim, and Hyosung Seol(KAERI) PDF보기 -
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Development of the the Numerical Code to Predict Wear Won Man Park, Sungman Son, and Choengryul Choi(Elsoltec), Tae Hyun Chun and Heung Seok Kang(KAERI) PDF보기 -
Last Modified : 1998-Autumn