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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) A Numerical Study on Heat Transfer Characteristics of Various Shapes of Fuel Rods in Nuclear Reactors Hyerim Woo, Sungjin Yang, and Jongrak Choi(KETI) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Development of CFD Simulation Methodology for Cladding Oxidation Phenomenon Siwon Seo, Armanto Simanjuntak, Benrico Simamora, and Jaeyoung Lee(HGU) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Sensitivity Study for Active Single Failure in the Intermediate Break LOCA Yerim Park, Seyun Kim, and Junkyu Song(KHNP) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Numerical Modeling of Flow Boiling in a Rectangular channel using OpenFOAM Iljin Kim and Hyungdae Kim(KHU) PDF보기 PPT보기
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) A Preliminary Study on Reliability Evaluation Methodology for Passive Safety Systems Youngjae Park, Jeehee Lee, and Seong-Su Jeon(FNC Tech.), Ju-Yeop Park(KINS) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Modeling the CRUD Effects on Heat Transfer in Subchannels of Pressurized Water Reactor Hyeon Ji Kim, Ji Yong Kim, and In Cheol Bang(UNIST) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Preliminary Analysis of PIUS-type Experimental Apparatus with Hot/Cold Fluids Interface for Inherently Safety Ju Hun Jung and In Cheol Bang(UNIST) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Safety Analysis of MicroURANUS LFR for Unprotected Loss of Flow and Unprotected Loss of Heat Sink Joo Hyung Seo and In Cheol Bang(UNIST) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Effects of Truly Optimized PWR Lattice Core Design on Reactor Power and Critical Heat Flux in a Natural Circulation Small Modular Reactor Jae Hyung Park, Jihun Im, Hyo Jun An, and Sung Joong Kim(HYU) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Performance Comparison of Compact Heat Exchangers Suitable for Chloride Molten Salt Fast Reactor Intermediate Heat Transport System Sunghyun Yoo, In Woo Son, Sungwook Choi, and Jeoing Ik Lee(KAIST) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Predictability Evaluation of SPACE for DVI Line Break Test with ATLAS Hae Min Park, Sung Won Bae, and Seung Wook Lee(KAERI) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Performance Evaluation of an AHX for Thermal Energy Storage System Test Loop In Sub Jun, Jung Yoon, and Hyeonil Kim(KAERI) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Preliminary Multi-Physcis Aanalysis of a 2x2 Rod Array Using CUPID/GIFT Coupled Code Yeong Hun Lee, Kyuseok Sim, Youho Lee, and Hyoung Kyu Cho(SNU) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) SB LOCA Analysis of a Floating Nuclear Reactor Under Combined Motion Condition Yujeong Ko, and Hyoung Kyu Cho(SNU), Han Rim Choi(KEPCO E&C) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Evaluation the Effect of Surface Roughness of Cr-coated Cladding with Multi-layer Model on Large Break-Loss of Coolant Accident Dong-Young Lee, Tae-Sun Ro, Bub-Dong Chung, and Soon-Joon Hong(FNC Tech.) PDF보기 -
Last Modified : 1998-Autumn