학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 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 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Mechanical Property Evaluation of Proton Irradiated Inconel X-750 | Sangeun Kim, Hyung-Ha Jin, I Seul Ryu, and Gyeong Geon Lee(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Evaluation of the Effect of Debris Clogging in the Fuel Bottom Nozzle on Fuel Performance | Taehyeon Kim and Donghee Lee(KHNP) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | FAC Assessment for SA106 Pipe with Elbows and Welds | Dong-Jin Kim, Sung-Woo Kim, Jong Yeon Lee, Kyung Mo Kim, Se Beom Oh, Gyeong Geun Lee, Jongbeom Kim, Seong-Sik Hwang, Min Jae Choi, Yun Soo Lim, Sung Hwan Cho, and Hong Pyo Kim(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Development of Empirical Stress Correction Factor for Creep-Rupture Model of Alloy 690 Steam Generator Tube | Jongmin Kim, Minchul Kim, and Joonyeop Kwon(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | Identification of Magnetite Scale in Eggcrate Support Plate Region of Steam Generator Tube from MRPC Probe Eddy Current Signals | Deok-Hyun LEE, Se-Beom OH, and Kyung-Mo KIM(KAERI) | PDF보기 | - |
| 2021-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu)~5.14(Fri) | On-line | On the Synergistic Effects of Helium and Hydrogen in Bubble Formations and Materials Degradation | Sangeun Kim and Hyung-Ha Jin(KAERI), Hyeongchul Kim, Jinhyeok Kim, Chansun Shin(Myongji Univ.), Joonoh Moon and Chang-Hoon Lee(KIMS) | PDF보기 | PPT보기 |
Last Modified : 1998-Autumn
