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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2025-Spring 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.22(Thu) 13:00 Lobby Methodologies for Acoustic Induced Vibration Analysis of Reactor Vessel Internals at Fluid-Structure Interfaces Chiwoong Ra, Hyungyu Roh, and No-cheol Park(Yonsei Univ.) PDF보기 -
2025-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 09:00 301 Experimental Investigation of Air-water Two-phase Flow through Inclined Circular Channel with Wire-mesh Sensor: Preliminary Test Hyukjae Ko, Taehwi Kim, Goon-Cherl Park, and Hyoung Kyu Cho(SNU) PDF보기 -
2025-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 09:20 301 Reduction of Radiative Heat Loss in Small Modular Reactors Through Thermal Radiation Shielding: An Experimental and CFD Approach Beomjin Jeong, Geunyoung Byeon, Namgook Kim, and Sung Joong Kim(HYU) PDF보기 -
2025-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 09:40 301 Local Thermal Analysis using an Optical Fiber Eemperature Sensor in a Flow Boiling Heat Transfer Donghwi Lee, Hyeon Taek Nam, and Seungro Lee(Jeonbuk National Univ.) PDF보기 -
2025-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 10:00 301 Experimental Investigation of Radiative and Convective Heat Transfer Coefficients in a Metal Containment Vessel for Small Modular Reactors under Steady-State Conditions Geunyoung Byeon, Beomjin Jeong, Namgook Kim, JinHo Song, JoonEon Yang, and Sung Joong Kim(HYU) PDF보기 -
2025-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 10:20 301 Preliminary Experiment on Individual Hydrogen Bubble Behaviors in Alkaline Water Electrolysis Seheun Kwon, Seungju Lee, Shinil Kim, and Haekyun Park(Kyungpook National Univ.) PDF보기 -
2025-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 11:00 301 Experimental Investigation on Augmentation of Critical Current Density in Alkaline Water Electrolysis using Shroud Structure Jaeduck Seo, Jeonghun Seo, and Haekyun Park(Kyungpook National Univ.) PDF보기 -
2025-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 11:20 301 Measurements of Bubbly Flow on a 4x4 Rod Bundle Under Oscillating Conditions Tan Hung Hoang, Myung Ho Kim, and Byoung Jea Kim(Chungnam National Univ.) PDF보기 -
2025-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 11:40 301 Experimental Observation of Bubble Behavior and CHF on a Downward-Facing Surface in Pool Boiling Young Hee Kim, Young Hoon Jeong, and Dong Hun Shin(KAIST), Min Suk Lee(Texas A M Univ.), Dong Hoon Kam(Argonne National Laboratory) PDF보기 -
2025-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 09:00 302 Analytical and Numerical Evaluation of Wall Thermal Boundary Conditions in Free Convective Thin Plates with Internal Heat Generation Moon Won Song(Jeonbuk National Univ.) PDF보기 -
2025-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 09:20 302 Development of Virtual Nuclear Reactor for Design and Demonstration of SMRs Yun Je Cho, Sung Hoon Choi, and Seong Ju Do(KAERI) PDF보기 -
2025-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 09:40 302 Numerical Analysis of Core Melt Solidification and Spreading Behavior Using the MPS Method Cho Yun-Sik, Kim Sung Joong, and Song JinHo(HYU) PDF보기 -
2025-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 10:00 302 Conceptual Problem-Based Verification of the Containment Thermal-Hydraulics Analysis Module for Severe Accident Analysis Kum Ho Han, Jehee Lee, and Yeon-Jun Choo(FNC Tech.) PDF보기 -
2025-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 10:20 302 Reactor Power and Thermal Safety Margin in a Natural Circulation Small Modular Reactor Adopting TOP Lattice Core Design Jae Hyung Park, Yujin Kim, Hyo Jun An, Jihun Im, JinHo Song, and Sung Joong Kim(HYU) PDF보기 -
2025-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.22(Thu) 11:00 302 CFD of Two-Phase Natural Circulation in the Presence of Non-Condensable Gas Nam Kyu Ryu and Byeong Jae Kim(Chungnam National Univ.) PDF보기 PPT보기
Last Modified : 1998-Autumn