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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2026-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 14:10 203 Quantitative Raman-Based Phase Fraction Analysis of Ce-Doped Gadolinia under Heavy-Ion Irradiation Hojin Ryu, Hakjun Lee, and Hyeongjin Kim(KAIST), and Seunghyeon Lee(KAERI) PDF보기 -
2026-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 14:50 203 Performance Analysis of B4C-Al2O3 Burnable Absorber for SMR JangSoo OH, YoungIn KIM, and HyoChan KIM(KAERI) PDF보기 -
2026-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 15:10 203 Mechanical, Physical and Thermal Properties of Titanium-Based Neutron Absorbing Structural Material Produced on a Large Scale Young-Bum Chun, Ji-Hoon Kang, Sun-Young Park, Seungmun Jung, and Younguk Lee(KAERI) PDF보기 -
2026-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 15:30 203 Criticality Safety Analysis of Advanced Neutron Absorbers for LEU+ Spent Fuel Pool Yujin Yang and Hwasung Yeom(POSTECH) PDF보기 -
2026-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.8(Fri) 09:00 203 Evaluation of Cladding Stress Effect According to Pellet MPS Type and Size using Finite Element Analysis Yunseog Nam, Gyeongha Choi, and Hakkyu Yoon(KEPCO NF) PDF보기 -
2026-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.8(Fri) 09:20 203 Hydride Reorientation Under Normal Operating Conditions: Roles of Plastic Deformation and PCMIInduced Hoop Stress JUNHEE LIM and YOUHO LEE(SNU) PDF보기 -
2026-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.8(Fri) 09:40 203 Complex Precipitate Engineering for High-Temperature Stability in Additively Manufactured FeCrAl Alloys Omer Cakmak, Hwasung Yeom, and Jung-Wook Cho(POSTECH) PDF보기 -
2026-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.8(Fri) 10:00 203 Safety Implications of Cr-Coated ATF Cladding: Realizable Benefits and Inherent Limitations SungHoon Joung and Youho Lee(SNU) PDF보기 -
2026-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.8(Fri) 10:20 203 High-temperature Steam Oxidation Behavior of Cr-coated Zr Alloy Cladding with Surface Cracks Youngbeen Yoon, Dongju Kim, and Youho Lee(SNU) PDF보기 -
2026-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.8(Fri) 11:00 203 Predicting the Terminal Solid Solubility of hydrogen in Zirconium Using the Phase-Field Method Kunok Chang and Sanghyun Ji(KHU) PDF보기 -
2026-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.8(Fri) 11:20 203 Hydrogen Effect on Phase Transition Temperature of HANA-6 TIAN CHEN, DONGJU KIM, and YOUHO LEE(SNU) PDF보기 -
2026-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.8(Fri) 11:40 203 Study on Pellet-Cladding Mechanical Interaction Behavior Using EDC-DIC Experiment and FE Analysis Jungju Lee and Byoungjae Kim(CNU), Sung-Uk Lee and Hyochan Kim(KAERI) PDF보기 -
2026-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.8(Fri) 12:00 203 Development of a Multi-layer Cr Coating Structure Model for ATF Cladding and Potential Incorporation of Coating Cracking Model Supported by Experimental Investigation Hyuntaek Rho and Youho Lee(SNU) PDF보기 -
2026-Spring 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 13:00 Lobby Synthesis of High-Purity UCl₄ via a BiCl₃-Based Chlorination Route for Chloride Molten Salt Reactors Younghwan Jeon, Dalsung Yoon, and Chang Hwa Lee(KAERI) PDF보기 -
2026-Spring 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 13:00 Lobby Effect of Sintering Atmosphere on the Microstructure of High Gd2O3 UO2 Nuclear Fuel Ji Hwan Lee, Jae Ho Yang, Dong-Joo Kim, Yun Song Jung, Ji-Hae Yoon, Hyeong Jin Kim, and Dong Seok Kim(KAERI) PDF보기 -
Last Modified : 1998-Autumn