학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2023-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 14:20 | 202B (2F) | Corrosion Study of Hastelloy N with Electrochemical Impedance Spectroscopy in NaCl-MgCl2-NiCl2 Systems | Jun Woo Park and Jong-Il Yun(KAIST) | PDF보기 | - |
| 2023-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 15:00 | 202B (2F) | Effect of Metal-assisted Chemical Purification on Corrosion in Molten Chloride Salts of Stainless Steel | Hyeon-Geun Lee, Jung-Min Kim, Taeho Kim, and Daejong Kim(KAERI) | PDF보기 | - |
| 2023-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 15:20 | 202B (2F) | Corrosion Behaviors of 3-D Printed Ni-based Alloy in Molten NaCl-MgCl₂ Salt | Younghwan Jeon, Hyeongjin Byeon, Kiwon Kang, and Jaeyeong Park(UNIST) | PDF보기 | - |
| 2023-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 13:40 | 203 (2F) | PM-HIP Manufacturing Method for Nuclear Reactor Components | Jinsung Jang, Seung Ho Joo, Min-Chul Kim, and Jong Min Kim(KAERI) | PDF보기 | PPT보기 |
| 2023-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 14:00 | 203 (2F) | Effect of Scan Strategy of SA508 Gr.3 Constituting Reactor Pressure Vessel on Mechanical Properties in Directed Energy Deposition | Wonjong Jeong and Ho Jin Ryu(KAIST), Young-Bum Chun, Suk Hoon Kang, Chang Kyu Rhee, and Min-Chul Kim(KAERI), Chang Hyoung Yoo, Seongjin Yoo, and Hongmul Kim(HANA amt) | PDF보기 | - |
| 2023-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 14:20 | 203 (2F) | Evaluation of Thermal Ageing Behavior of an Alumina-forming Duplex Stainless Steel (ADSS) Alloy at 375℃ and 400℃ | Chaewon Kim, Sumin Kim, and Changheui Jang(KAIST) | PDF보기 | - |
| 2023-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 15:00 | 203 (2F) | Elasto-Plastic Analaysis in the Simulation of the Piping System in Nuclear Power Plants | ChiWoong Ra, Eun-ho Lee, Hyunkyu Roh, Jeonghyun Kim, and No-cheol Park(Yonsei Univ.) | PDF보기 | - |
| 2023-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 15:20 | 203 (2F) | Effect of Stress State and Load Ratio on the Ratchet Deformation of SA508 Gr.1a LAS and SA312 TP316 SS | Sang Eon Kim and Jin Weon Kim(CSU), Jong Sung Kim(Sejong Univ.) | PDF보기 | - |
| 2023-Spring | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Fri) 09:00 | 202B (2F) | Effect of Fission Gas Diffusivity of Dopant in Cr2O3 Doped UO2 Pellet | JangSoo Oh, YangHyun Koo, and HyoChan Kim(KAERI) | PDF보기 | - |
| 2023-Spring | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Fri) 09:20 | 202B (2F) | Development and Various Nuclear Fuel Applications Status of Accident Tolerant Fuel Pellet Technology with Enhanced Thermal Conductivity | Dong-Joo Kim, Dong Seok Kim, Jae Ho Yang, Heung Soo Lee, Ji-Hae Yoon, Ji-Hwan Lee, and Hyun-Gil Kim(KAERI) | PDF보기 | - |
| 2023-Spring | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Fri) 10:00 | 202B (2F) | Fabrication of CSBA-loaded UO₂ Fuel Pellets for HANARO Irradiation Test | Dong Seok Kim, Ji Hwan Lee, Dong-Joo Kim, Jae Ho Yang, Ji-Hae Yoon, Heung-Soo Lee, and Seongwoo Yang(KAERI), Ho Jin Ryu and Yonghee Kim(KAIST) | PDF보기 | - |
| 2023-Spring | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Fri) 10:20 | 202B (2F) | Preliminary Assessment of La2O3-Al2O3-SiO2 Doped ATF and Evaluation of Cycle Length Compensation by Enrichment Adjustment | Kibeom Park, Tongkyu Park, and Sung-kyun Zee(FNC Tech.) | PDF보기 | - |
| 2023-Spring | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Fri) 11:00 | 202B (2F) | Fuel Performance Code for Light Water Reactor, GIFT: Current Development Status and Path-forward | Kyuseok Sim and Youho Lee(SNU) | PDF보기 | - |
| 2023-Spring | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Fri) 11:20 | 202B (2F) | Integral LOCA Experiment to Study FFRD Phenomena of High Burnup ATF Clad Fuels | Hyunwoo Yook, Sunghoon Joung, Boyeon Kweon, and Youho Lee(SNU) | PDF보기 | - |
| 2023-Spring | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Fri) 11:40 | 202B (2F) | Thermal-mechanical Analysis of Lead-cooled Fast Reactor Fuel Assembly with the Inverted Core Design | Hyeong Jin Kim, JiWon Mun, and Ho Jin Ryu(KAIST) | PDF보기 | - |
Last Modified : 1998-Autumn
