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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2025-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.23(Fri) 11:00 301 Assessment of Conservative Core Conditions for LBLOCA in APR1400 using TRACE Code Hyungjoo Seo and Byung Gil Huh(KINS) PDF보기 -
2025-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.23(Fri) 11:20 301 Review of the Performance Features of Containment Evacuation System in Integral Pressurized Water Reactor Soon-Joon HONG, HyeonMin SEO, Jan HRUSKOVIC, and Bud-dong CHUNG(FNC Tech.) PDF보기 -
2025-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.23(Fri) 11:40 301 Development of 2D (r-θ) Heat Conduction Model for Fuel Rod in FAMILY Joosuk Lee, Seulbeen Kim, and Jang Keun Park(KINS) PDF보기 -
2025-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.23(Fri) 09:00 302 Effects of Group Constant Model on Multi-physics Analysis of Fast-spectrum Molten Salt Reactor with Beryllium Oxide Reflector Wooseong Park and Yong Hoon Jeong(KAIST) PDF보기 -
2025-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.23(Fri) 09:20 302 Parametric Effects of Helical Coil Heat Exchanger Design on Thermal-Hydraulic Performance of Passive Molten Salt Fast Reactor Seungmin Lee, Dowon Lee, Juhyeong Lee, and Sung Joong Kim(HYU) PDF보기 -
2025-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.23(Fri) 09:40 302 Melting Points Comparison of Chloride Salts for Coolant of Molten Salt Fast Reactor Sunghyun Yoo and Jeong Ik Lee(KAIST) PDF보기 -
2025-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.23(Fri) 10:00 302 Design of the Heat Exchanger for Passive Molten Salt Fast Reactor using GAMMA+ Dowon Lee, Juhyeong Lee, Seungmin Lee, Jihun Im, JinHo Song, and Sung Joong Kim(HYU) PDF보기 -
2025-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.23(Fri) 10:20 302 Considerations for Performance Parameters in Design of Passive ECCS Valves through Dynamic Response Analysis Young Seok Bang, Youngjae Park, You Cho Choi, Seong-Su Jeon, and Soon-Joon Hong(FNC Tech.) PDF보기 -
2025-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.23(Fri) 10:40 302 Investigation of Freeze Valve Release Models Applicable for Molten Salt Reactor by OpenFOAM Code Juhyeong Lee, Ye Hwan Chun, and Sung Joong Kim(HYU) PDF보기 -
2025-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 13:00 Lobby Integral Effect Test on a Loss of Safety Injection Accompanied by a Small Break Loss of Coolant Accident based on the Risk/Performance Information Yusun Park, Byoung Uhn Bae, Jae Bong Lee, Jun Yeong Jung, Jongrok Kim, Seok Cho, and Kyoung Ho Kang(KAERI), Jea Beol Hong and Hyun Bin Chang(FNC Tech.) PDF보기 -
2025-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 13:00 Lobby Experimental Study on Head Degradation in a Reactor Coolant Pump for a Small Modular Reactor under Two-Phase Flow Conditions Byeonggeon Bae, Tae-Kyoon Kim, Hyuntae Lim, and Jihoon Lee(KAERI) PDF보기 -
2025-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 13:00 Lobby Preliminary Testing of the Flow Loop in a High-Pressure Flow Boiling Test facility for a PWR Subchannel Chanmin Jeong, Banseok Bae, Ahyeong Cho, Jongwhi Choi, and Hyungdae Kim(KHU) PDF보기 -
2025-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 13:00 Lobby Thermal Analysis of Micro-pillar Structures under Pool Boiling Conditions using Optical Fiber Sensors Minkyu Park, Hyeon Taek Nam, Seungro Lee, and Donghwi Lee(Jeonbuk National Univ.) PDF보기 -
2025-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 13:00 Lobby Experimental Investigation of Heat Transfer Characteristics of Multiple Heat Pipe with Inclination Myung Jin Jeong, Ye Sung Kim, and Hyoung Kyu Cho(SNU) PDF보기 -
2025-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 13:00 Lobby Coupled Analysis of High-Resolution Localized Temperature Measurement Using an Optical Fiber Sensor and Bubble Dynamics in Pool Boiling Seoyeon Park, Hyeonmin Choi, and Hyungmo Kim(Gyeongsang National Univ.), Dong Eok Kim(CAU) PDF보기 PPT보기
Last Modified : 1998-Autumn