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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2026-Spring 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 09:00 Halla Hall A Numerical Evaluation of Displacement-Robust and Fault-Tolerant Four-Sensor Probe Arrays for Local Bubble Parameter Measurement in Two-Phase Flow Minhong Cho, XuanQuyet Do, Jinyeong Bak, Jae Jun Jeong, and Byongjo Yun(PNU) PDF보기 -
2026-Spring 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 09:20 Halla Hall A Experimental Investigation of Upward and Downward Mixed Convection in Water Flows using an Optical Fiber Sensor Sungkun Chung, Jihun Kim, Jeong Hyeon Oh, and HangJin Jo(POSTECH) PDF보기 -
2026-Spring 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 09:40 Halla Hall A Effect of Compressible Volume on Pressure Drop Oscillations in a Vertical Annular Channel under Subcooled Flow Boiling Conditions Jihwan Mun and Taeseok Kim(JNU) PDF보기 -
2026-Spring 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 10:00 Halla Hall A Preliminary Experimental Evaluation of Cascading Failure in Multi Heat Pipe Test Facility Joo Hyung Seo, Ji Sung Oh, and In Cheol Bang(UNIST) PDF보기 -
2026-Spring 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 10:20 Halla Hall A Experimental Study on the Thermal Performance of a Sodium Heat Pipe Assembly for Space Nuclear Reactors Sin-Yeob Kim, In Woo Son, Minkyu Lee, Byung Ha Park, and Chan Soo Kim(KAERI) PDF보기 -
2026-Spring 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 11:00 Halla Hall A Fundamental Experimental Study and Preliminary Heat Loss Estimation of a Vertical Sodium Heat Pipe with Hybrid Wick Minkyu Lee, Sin-Yeob Kim, In Woo Son, Byung Ha Kim, and Chan Soo Kim(KAERI) PDF보기 -
2026-Spring 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 11:20 Halla Hall A Structural Analysis of Heater Rods with Different Groove Shapes under Pressurized Conditions Jihun Kim, SeHyeon Park, and HangJin Jo(POSTECH), Sungjin Kwon(NFRI) PDF보기 -
2026-Spring 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 11:40 Halla Hall A Development of an Experimental Facility and Modeling Strategy for Jet Impingement Heat Transfer under i-SMR LOCA Conditions Yonadan Choi and Yong Hoon Jeong(KAIST) PDF보기 -
2026-Spring 5C : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 09:00 303B Technical Requirements for CFD Analysis in Validating Fuel Assembly CHF Test Results Jong Chull Jo and Hiwon Lee(TIUM solutions) PDF보기 -
2026-Spring 5C : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 09:20 303B Heatmap-Based Similarity Mapping and Real-Gas Model Selection for sCO2 Turbomachinery Seungkyu Lee and Jeong Ik Lee(KAIST) PDF보기 -
2026-Spring 5C : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 09:40 303B Performance Evaluation of the GPU-Parallelized CUPID Code for Large-Scale Reactor Thermal-Hydraulic Simulation So-Hyun Park, Ik Kyu Park, and Il Jin Kim(KAERI) PDF보기 -
2026-Spring 5C : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 10:00 303B Preliminary CFD of Boron Mixing in the i-SMR under a Natural Circulation Seung Hyup Ji, Nam Kyu Ryu, and Byoung Jae Kim(CNU), YoungLong Lee(KEPCO E&C) PDF보기 -
2026-Spring 5C : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 10:20 303B Comparative Analysis of 1D MARS-KS and 3D CFD Modeling for Thermal-Hydraulic Characteristics of i-SMR Helical Coil Steam Generator Je-Hyeong Park, Won-Seok Ryoo, and Jae-Ho Jeong(CAU) PDF보기 -
2026-Spring 5C : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 11:00 303B Evaluation of Radiative Heat Transfer within Steel Containment Vessel of Small Modular Reactor Jong Hui Lee, Minkyu Lee, Hun Sik Han, and Kwanghyun Ahn(KAERI) PDF보기 -
2026-Spring 5C : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 11:20 303B Development of a Mechanistic Condensation-Liquid Film Coupled Model and Its Application to Forced-Convection Condensation of Superheated Steam Hyung Jun Kim, Jeong Hun Kang, and Yeon-Gun Lee(Sejong Univ.), Jia Yu(KEPCO E&C) PDF보기 -
Last Modified : 1998-Autumn