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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2026-Spring 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 09:40 203 Full Fuel Cycle Technoeconomic Analysis and Core Design Strategies for 24-Month High-Burnup PWRs Using LEU+ Fuel Hyeongtak Kang, Chansoo Lee, SungHoon Joung, Seungmin Kwak, and Youho Lee(SNU) PDF보기 -
2026-Spring 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 10:00 203 Burnup-Dependent Full-Core Sensitivity Analysis of PWR Fuel Performance to Fuel Properties and Design Parameters Donguk Kim and Youho Lee(SNU) PDF보기 -
2026-Spring 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 10:20 203 Development Status of GIFT-2.0: An Extended Fuel Performance Code for Burnup-Dependent Transient and Accident Analysis Kyuseok Shim and Youho Lee(SNU) PDF보기 -
2026-Spring 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 11:00 203 Development of Machine Learning Potential and Investigation of Diffusion Behavior in UO₂ via Molecular Dynamics Simulations Jiwoo Kim and Ho Jin Ryu(KAIST) PDF보기 -
2026-Spring 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 11:20 203 Effects of Carbon Black Dispersion on Oxycarbide Fuel Kernels Minseok Lee, Injin Sa, and Eung-Seon Kim(KAERI) PDF보기 -
2026-Spring 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 11:40 203 TRIPLE: A 3D Finite Element Code for TRISO Fuel and Its Application to HTGR Design and Multiscale Fuel Analysis Jongho Park and Youho Lee(SNU) PDF보기 -
2026-Spring 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 12:00 203 Fission Gas Adsorbents in PWR Fuel Rod Plenum for Mitigation of High-Burnup Rod Internal Pressure: Experimental Feasibility Study and Fuel Performance Simulation Eunchae Sim and Youho Lee(SNU) PDF보기 -
2026-Spring 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 13:30 202B Mechanistic Modeling of Protection Loss and Embrittlement Behavior of Cr-Coated Zirconium Alloy Cladding ATF under High-Temperature Steam Oxidation Dongju Kim and Youho Lee(SNU) PDF보기 -
2026-Spring 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 13:50 202B Development of a PCI Analysis Framework Using Cumulative Damage Index (CDI) Model in Smeared-Pellet Fuel Performance Codes and Its Application to the Load-Following PWR Fuel Safety Assessment Dongki Lee, Chansoo Lee, Hyeongtak Kang, and Youho Lee(SNU) PDF보기 -
2026-Spring 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 14:10 202B Explainable Machine Learning for Mechanistic Analysis of Irradiation-Induced Tensile Behavior in Fast Reactor Cladding Hongin Kim and Young-Kook Lee(Yonsei Univ.), Sunghwan Yeo, Jun-Hwan Kim, Jeong Mok Oh(KAERI) PDF보기 -
2026-Spring 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 14:50 202B Thermodynamic Modeling of MCl - CrCl3 (M = Na, K) Systems and Prediction of Chromium Dissolution in Chloride Molten Salts SungMin Yeo, YongJin Cho, TaeHyong Kim, and InHo Jung(SNU) PDF보기 -
2026-Spring 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 15:10 202B Explosion Analysis of Nuclear Fuel Cladding using PINN-based Predicted Material Properties Yong Gyun Shin, Hyeon-Su You, and Yoon-Suk Chang(KHU) PDF보기 -
2026-Spring 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 15:30 202B Thermodynamic Modeling Progress of Uranium Chloride and Uranium Oxide Systems YongJin Cho, TaeHyoung Kim, and In-Ho Jung(SNU) PDF보기 -
2026-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 13:30 203 Hydration Resistance and Chemical State Analysis of Zirconia-doped Gadolinia Burnable Absorber Hyeongju Bae and Ho Jin Yu(KAIST), Hyeong Jin Kim(KAERI) PDF보기 -
2026-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.7(Thu) 13:50 203 Effect of 15% Er2O3 and Dy2O3 Doping on the Gd2O3 Crystal Structure at Elevated Temperature Anissa Isnaini, Akmal Muhammad, and Ho Jin Ryu(KAIST) PDF보기 -
Last Modified : 1998-Autumn