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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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 -
2024-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.9(Thu) 15:00 303A (3F) Emulating Neutron Irradiation Effect on Stainless steel by Non-Irradiation Method Hyeonje Ryoo, Junhyuk Ham, and Ji Hyun Kim(UNIST) PDF보기 PPT보기
2024-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.9(Thu) 15:20 303A (3F) Protection of the Structural Materials of MSR Through Ni-coating Younghwan Jeon(KAERI), Kyeongtae Park and Jaeyeong Park(UNIST) PDF보기 -
2024-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.10(Fri) 09:00 302 (3F) Researches on Nuclear Fuel Pellets and Neutron Absorbers with an Overview of the Irradiation Tests at KAERI Dong Seok Kim, Dong-Joo Kim, Jae Ho Yang, Ji-Hae Yoon, Ji Hwan Lee, and Seongwoo Yang(KAERI) PDF보기 -
2024-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.10(Fri) 09:20 302 (3F) Oxidation Behavior in High Temperature Steam Environments of Liquid Phase Sintered Silicon Carbide Ceramics for TRISO-Based Accident Tolerant Fuel Kwang-Young Lim, Yeon-Soo Na, Tae-Sik Jung, Min-Jae Ju, Hun Jang, and Yoon-Ho Kim(KEPCO NF) PDF보기 -
2024-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.10(Fri) 09:40 302 (3F) Comprehensive Study on the Loss of Protectiveness Behavior in Cr-Coated ATF in HighTemperature Steam Oxidation Dongju Kim and Youho Lee(SNU) PDF보기 -
2024-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.10(Fri) 10:00 302 (3F) Development of Advanced Hydride Reorientation Model and Experimental Validation Changhyun Jo and Youho Lee(SNU) PDF보기 -
2024-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.10(Fri) 10:40 302 (3F) Preliminary Study of Sensitivity Analysis for IFA-650.9 Experiment with MERCURY Fuel Performance Code Hyochan Kim, Changhwan Shin, Sung-Uk Lee, and Donghwa Lee(KAERI) PDF보기 -
2024-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.10(Fri) 11:00 302 (3F) Ballooning, Burst and Oxidation Behavior of Cr-coated ATF Cladding in during LOCA Hyunwoo Yook, SungHoon Joung, and Youho Lee(SNU) PDF보기 -
2024-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.10(Fri) 11:20 302 (3F) Effect of Coating Material and Oxidation Model on the Fuel Performance Of Accident-Tolerant Fuel (ATF) with Multi-layered Cladding Jiwon Mun, Hyeong-Jin Kim, and Ho Jin Ryu(KAIST) PDF보기 -
Last Modified : 1998-Autumn