학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2024-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 09:00 | 303A (3F) | Development of Nanostructured Ferritic Alloy (NFA) Fuel Cladding Tubes using Cold Spray Deposition Technology | Hwasung Yeom(POSTECH), Kumar Sridharan(University of Wisconsin-Madison) | PDF보기 | - |
| 2024-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 09:20 | 303A (3F) | Evaluation of Mechanical Properties and Helium Swelling Response of Ti/Ta-RAFM Steels under Fe Ion Irradiation and Helium Implantation | Sangeun Kim, Jinwoo Park, and Chansun Shin(Myongji Univ.), Hyung-Ha Jin(KAERI), Chang-Hoon Lee(KIMS) | PDF보기 | - |
| 2024-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 09:40 | 303A (3F) | Development for Fe-Cr-Ni-based Structural Materials on the Molten Salt Reactor | Jeonghwan Lee and Kunok Chang(KHU) | PDF보기 | - |
| 2024-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 10:00 | 303A (3F) | Corrosion Behavior of High Aluminum Stainless Steels in Cl-based Molten Salt Environment | Sumin Kim, Hyun Joon Eom, and Changheui Jang(KAIST), Won Seok Lee(SNU) | PDF보기 | - |
| 2024-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 10:20 | 303A (3F) | Development Strategy of Molten Chloride Salt Corrosion Resistive Ni Superalloy | Hyeon-Geun Lee, Chaewon Kim, Jung-Min Kim, Daejong Kim, Byung-Hyuk Jun, Ji-Hyun Yoon, and Junhyun Kwon(KAERI) | PDF보기 | - |
| 2024-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 11:00 | 303A (3F) | Development of Alumina-Forming Ni-base Alloys as Structural Materials for Molten Salt Reactors | Chaewon Kim, Hyeon-Geun Lee, Ji-Hyun Yoon, Byung-Hyuk Jun, and Daejon Kim(KAERI) | PDF보기 | - |
| 2024-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 11:20 | 303A (3F) | JIc Prediction Model Based on Microstructure and Strength for SA508 Gr.1A Low-Alloy Steel | Se-Mi Hyun and Seok Su Sohn(Korea Univ.), Seokmin Hong, Min-Chul Kim, and Jongmin Kim(KAERI) | PDF보기 | - |
| 2024-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 11:40 | 303A (3F) | Automation of Pre-Cracking Without Additional Sensors for CT Specimens | Bong-Sang Lee, Min-Chul Kim, and Jong-Min Kim(KAERI) | PDF보기 | - |
| 2024-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 12:00 | 303A (3F) | Impact of In-Situ Synthesized Nitride and Oxide Precipitates on L-PBF Fe-12Cr-6Al as ATF Candidate Material | Omer Cakmak, Hwasung Yeom, and Jung-Wook Cho(POSTECH) | PDF보기 | - |
| 2024-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 13:30 | 302 (3F) | Machine Learning Approach for Extracting Uranium Nonuniform Distribution in U-Zr-RE Metallic Fuel Slugs Induced by Immiscibility | Seung Uk Mun, Jung Su Ahn, Sang-Gyu Park, Soo Min Nam, and Jun Hwan Kim(KAERI), Byung Mook Weon(Sungkyunkwan Univ.) | PDF보기 | - |
| 2024-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 14:00 | 302 (3F) | Exploring the Maximum Allowable Oxidation and Peak Cladding Temperature Limits of Cr Coated Accident Tolerant Fuel Cladding | SungHoon Joung and Youho Lee(SNU) | PDF보기 | - |
| 2024-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 14:20 | 302 (3F) | Evaluation of Creep-Based Deformation Model in FRAPTRAN-KATF for In-situ Cladding Ballooning Measurement Data | Changhwan Shin, Sung-Uk Lee, and Hyochan Kim(KAERI) | PDF보기 | - |
| 2024-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 15:00 | 302 (3F) | TRISO Temperature Distribution Simulation using MOOSE Framework | Jiho Kim and Kunok Chang(KHU) | PDF보기 | - |
| 2024-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 15:20 | 302 (3F) | Validation of Cs Diffusion Behavior in UO2 for Accident Tolerant Fuels with Moment Tensor Potentials | Jiwoo Kim, Hyeongseob Kim, and Ho Jin Ryu(KAIST), Jae Joon Kim(KAERI) | PDF보기 | - |
| 2024-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 13:40 | 303A (3F) | Atomic Scale Insights into Flow-Accelerated Corrosion of SA106 Gr.B Carbon Steel in Simulated Secondary Water | Do Haeng Hur and Jeoh Han(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
