학술발표회 논문집 (ISSN: 3140-1864)
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2026-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 10:00 | 202B | Multiphysics Simulation of Flow-Assisted Erosion in the Secondary System Piping of i-SMR | Homin Yu and Kunok Chang(KHU) | PDF보기 | - |
| 2026-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 10:20 | 202B | Methodologies of Added Mass Consideration in Fluid–Structure Interaction and Its Influence on Reactor Vessel Internal Dynamics | Chiwoong Ra, Youngjin Park, and No-cheol Park(Yonsei Univ.) | PDF보기 | - |
| 2026-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 11:00 | 202B | Evaluation of Flow-Accelerated Corrosion in Feedwater Systems under Flexible Operation Scenarios of Nuclear Power Plants | Jung Woo Kim, Ji Hun Kang, and Dae Young Lee(KEPCO E&C) | PDF보기 | - |
| 2026-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 11:20 | 202B | Collapse Pressure Evaluation of Helical Steam Generator Tubes Considering Geometric Characteristics and Temperature-Dependent Material Properties | Hyeon-Su You, Yong Gyun Shin, and Yoon-Suk Chang(KHU) | PDF보기 | - |
| 2026-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 11:40 | 202B | In-situ Synthesis of Oxide Dispersion Strengthened Alloy using Laser Powder-Directed Energy Deposition | Joowon Suh, Seungmun Jung, Young-Bum Chun, and Suk Hoon Kang(KAERI), Wonjong Jeong(KIMM), Heung Nam Han(SNU), Ho Jin Ryu(KAIST), Hee-Suk Chung and Sang Sub Han(KBSI) | PDF보기 | - |
| 2026-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 09:00 | 203 | Development of a Novel Phase-Field Model for Fission Gas Bubble Swelling in UO2 Nuclear Fuel | Changhyun Jo and Youho Lee(SNU), Vishal Yadav and Michael Tonks(Univ. of Florida) | PDF보기 | - |
| 2026-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.7(Thu) 09:20 | 203 | Simulation of OECD/NEA FIDES-II LOC-C-4 experiment practice by MERCURY V1.0 | Hyochan Kim, Sung-uk Lee, Jang-soo Oh, and Donghwa Lee(KAERI) | PDF보기 | - |
| 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 | - |
Last Modified : 1998-Autumn
