학술발표회 논문집 (ISSN: 3140-1864)
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2021-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.14(Fri) 10:15 | On-line | Improvement of Alkali Silicate Heat-Resistant Coating According to ZIRLO’s Surface Treatment Method | Boyeon Kweon, Gyu Hyeon Shim, Ji Hoon Kim, Dong Ho Nguyen, and Ho Seon Ahn(INU) | PDF보기 | - |
| 2021-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.14(Fri) 10:40 | On-line | Post-LOCA Ductility of Cr-coated Cladding and Its Implications on Accident Coping Time | Hyunwoo Yook, Kyunghwan Keum, Dongju Kim, and Youho Lee(SNU) | PDF보기 | PPT보기 |
| 2021-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.14(Fri) 11:05 | On-line | Study on Fe-Cr-Al Alloys Corrosion on 360 ℃ Simulated Pressurized Water Chemistry Condition | Taeyong Kim, Seung Chang Yoo, Junhyuk Ham, Yunju Lee, In Young Song, and Ji Hyun Kim(UNIST), Sungyu Kim and Chi Bum Bahn(PNU) | PDF보기 | - |
| 2021-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.14(Fri) 11:30 | On-line | Air Oxidation Behaviors and Kinetics of UO2 and Zircaloy-4 Cladding under Spent Fuel Pool Accident Condition | Sun-Ki Kim(KAERI) | PDF보기 | - |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Surface Characteristics of Metal Fuel Rod Prepared by Using Quartz and Graphite Molds | Kyungchai Jeong, Sangkyu Park, and Jeongyong Park(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Preliminary Study on the Fretting Wear Behavior of Multi-Layer Coatings for Accident Tolerant Fuel Cladding | Young-Ho Lee, Jung-Hwan Park, Dong-Jun Park, Yang-Il Jung, Sung-Chan Yoo, and Hyun-Gil Kim(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | FRAPCON Base Irradiation Input for FFRD Analysis | Yong Sik Yang and Jang Soo Oh(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Qualitative Approach to Understand Irradiation Growth Behavior of ODS ATF fuel | Yong Sik Yang, Jong Dae Hong, and Jae Yong Kim(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Qualitative Approach to Understand the Behaviors of Oxidation, Hydriding, and the Buildup of Corrosion Products (CRUD) for CrAl-ODS-Zr Alloy ATF Cladding | Jong-Dae Hong and Jae Yong Kim(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Qualitative Approach to Understand Fatigue Behavior of CrAl-ODS-Zr Alloy ATF Cladding | Jong-Dae Hong and Jae Yong Kim(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Pressure Calculation of Intergranular Bubbles in UO2 | Jae joon Kim and Ho jin Ryu(KAIST) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Ramp Test Rods Analysis using ROPER and ABAQUS | Yun-seog Nam, Hak-kyu Yoon, and Jae-Myung Choi(KEPCO NF) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Analysis of IFA-650.5 LOCA Test : FFRD Analysis by using FRAPTRAN 2.0P1 Code | Jang Soo Oh and Yong Sik Yang(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Finite Element Analysis of Unit Cell Inverted Core Fuel for Micro Lead-cooled Fast Reactor | Ji Won Mun and Ho Jin Ryu(KAIST) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | A COPA Fission Product Release Analysis for a Gen-IV Numerical Calculation Case | Young Min Kim and Eung Seon Kim(KAERI) | PDF보기 | PPT보기 |
Last Modified : 1998-Autumn
