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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) 09:40 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 -
2024-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.9(Thu) 14:00 303A (3F) Evaluation of the Threshold Stress Inducing Hydride Reorientation in Zirconium Cladding Including Dislocation Loops Using Multiphase-field Method Wooseob Shin and Kunok Chang(KHU) PDF보기 -
2024-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.9(Thu) 14:20 303A (3F) Oxidation Behavior of Proton-irradiated 316 SS Prepared by Inclined Grinding Method Yun Soo Lim, Dong Jin Kim, Sung Sik Hwang, Sung Woo Kim, Min Jae Choi, and Jong Yeon Lee(KAERI) PDF보기 -
Last Modified : 1998-Autumn