학술발표회 논문집 (ISSN: 3140-1864)
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 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 | - |
| 2026-Spring | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 13:00 | Lobby | Fabrication of HTGR Fuel Compacts by Graphite Powder Compaction | Jae Joon Kim, Seok-Jin O, and Eung-Seon Kim(KAERI), Sanghyun Ji(KHU) | PDF보기 | - |
| 2026-Spring | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 13:00 | Lobby | Development and Validation of a FEM-Based One-Dimensional Model for Coupled Thermal–Oxidation Analysis of Plate-Type Nuclear Fuel (PROPER-COMSOL 1D) | Heung Soo Lee, Cheol Min Lee, and June-Hyung Kim(KAERI) | PDF보기 | - |
| 2026-Spring | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 13:00 | Lobby | 3D Finite Element Analysis of Thermal-Mechanical Behavior in Helical Cruciform Fuel | Yeon Sung Choi(PNU), Jiwon Mun and Ho Jin Ryu(KAIST) | PDF보기 | - |
| 2026-Spring | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 13:00 | Lobby | Sensitivity Analysis of CRUD Growth and Boron Hideout on Fuel Assemblies | Seungjin Seo(HDEC) | PDF보기 | - |
| 2026-Spring | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 13:00 | Lobby | Verification of Aluminum Cladding Oxide Growth Models in the PROPER Fuel Performance Code | Cheol Min Lee, Heung Soo Lee, and June-Hyung Kim(KAERI) | PDF보기 | - |
| 2026-Spring | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 13:00 | Lobby | Modeling for U-Zr Annular Metallic Fuel in SFR using COMSOL Multi-physics | Ju-Seong Kim, Heung Soo Lee, Cheol Min Lee, and June-Hyung Kim(KAERI) | PDF보기 | - |
| 2026-Spring | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 13:00 | Lobby | Monte Carlo-Based Estimation of TRISO Kernel Attenuation Factors for an HTGR Source-Term Analysis | Young Min Kim, Jae Joon KIm, Eung Seon Kim, and Chan Soo Kim(KAERI) | PDF보기 | - |
| 2026-Spring | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 13:00 | Lobby | Qualification Progress of Atomized U3Si2/Al Dispersion Fuel in KAERI | Tae Won Cho, Yong Jin Jeong, Dong Jun Park, and Jong Man Park(KAERI), Ann Leenaers, Jared Wight, and Beatriz Acevedo(SCK CEN) | PDF보기 | - |
Last Modified : 1998-Autumn
