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 | Effect of Trace Element Addition on Mechanical Properties and Corrosion Resistance in Ni-based Alloys for Molten Salt Reactor | Byung-Hyuk Jun, Chaewon Kim, Daejong Kim, and Hyeon-Geun Lee(KAERI) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Molecular Dynamics Simulation of Helium Diffusion in Nickel | Junhyun Kwon, Gyeong-Geun Lee, and Hyeon-Geun Lee(KAERI), Chaeyeong Kim and Takuji Oda(SNU) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Effects of Heavy Ion Irradiation on AlSc Alloys | Sung Eun Kim(Inha Univ.) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Irradiation Induced Creep in Al-Sc Alloys using In-Situ TEM Method | Sung Eun Kim(Inha Univ.) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Comparative Analysis of Crack Density of 20% and 35% Cold Rolled Type 304 SS according to Slow Strain Rate Test using IASCC Test Facility (ITF) Mock-up | Sung Hwan Cho and Sung Woo Kim(KAERI) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Machine Learning-Driven Prediction of Fe-(9-12)Cr Steel Properties for Nuclear Structural Applications | Hongin Kim(Yonsei Univ.|KAERI), Sunghwan Yeo, Sung Ho Kim, and Jun Hwan Kim(KAERI), Young-Kook Lee(Yonsei Univ.) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Damage-Induced Acceleration of Molten Salt Corrosion in Ni-Coated Alloys | Younghwan Jeon(KAERI), Kyeongtae Park and Jaeyeong Park(UNIST) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Prediction of Long-term Creep Strength and Negligible Creep Curve for Eurofer Steel | Woo-Gon Kim, Youngjin Roh, and Seonhwa Kim(KETG), Ki-Ean Nam and Hyeong-Yeon Lee(KAERI) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Investigation of High Temperature Hydrogen Degradation of Structural Materials in Nuclear Energy System | Junyeong Jo and Hwasung Yeom(POSTECH) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Predicting Hoop Mechanical Properties of Nuclear Fuel Cladding from the Ring Compression Test (RCT) Result | Low Wei Chen, Dahyeon Woo, and Youho Lee(SNU) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Finite Element Analysis of Stress Evolution at Metal-Oxide Interface during High Temperature Oxidation | Jaeheon Kim and Chi Bum Bahn(PNU) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Irradiation Capsule (24M-05K) Design for TP 304H Stainless Steel in HANARO | Kee-Nam Choo, Jong-Woo Kim, Hae-Sun Jeong, Seng-Jae Park, Yoon-Taek Shin, and Sung-Woo Yang(KAERI) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Uncertainty Evaluation Program of Specific Heat Measurement Data | Kweonho Kang, Jaesoo Ryu, and Changhwa Lee(KAERI), Changje Park(Sejong Univ.) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Nuclear and Thermal Sensitivity Analysis of a Double-Layer Thermal Medium Capsule in Neutron Irradiation Tests | Jong Woo Kim, Hae Sun Jeong, Junesic Park, Ye Eun Na, Ki Nam Choo, and Seong Woo Yang(KAERI) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Design Thickness Variation in i-SMR Reactor Vessels: A Comparison of ASME BPVC Sec. III Subsections NB and NE | Beom-jin Kim and Jin-Ha Hwang(Pukyong National Univ.) | PDF보기 | - |
Last Modified : 1998-Autumn
