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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2026-Autumn 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.29(Thu) 13:50 104 Implementation of Cr-Coated ATF Cladding Models in the Steady-State Fuel Performance Code FRAPCON Hyoungmun Kwon, Changhwan Shin, and Yongsik Yang(KAERI), Juyeop Park(KINS) PDF보기 -
2026-Autumn 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.29(Thu) 14:10 104 Prediction of Composition Evolution and Material Properties of Ag-In-Cd Absorbers for Flexible Operation of PWRs Hyeong Jin Kim, Dong Seok Kim, and Junho Moon(KAERI) PDF보기 -
2026-Autumn 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.29(Thu) 14:50 104 Development of High-Fidelity Analysis System for the Evaluation of Fuel Irradiation Tests in HANARO Seongwoo Yang, Sung-Jae Park, Junesic Park, and Ye-Eun Na(KAERI) PDF보기 -
2026-Autumn 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.29(Thu) 15:10 104 Analysis of the Oxidation State Change of High-Gd₂O₃-Content UO₂ Pellets in Simulated Fuel Rod Leakage Conditions Tae-sik Jung, Seong-woo Ha, Chae-rin Kim, Yeon-soo Na, Min-jae Ju, and Kwang-young Lim(KEPCO NF) PDF보기 -
2026-Autumn 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.30(Fri) 09:00 105 A Review of Magnetite-Accelerated Corrosion of Secondary Side Materials in PWRs Do Haeng Hur and Soon-Hyeok Jeon(KAERI), Yeong Ho Son and Geon Dong Song(FNC Tech.), Jeoh Han(KHNP) PDF보기 -
2026-Autumn 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.30(Fri) 09:20 105 Superhydrophilic Nanoporous Oxide Surface on Zr Alloy for CRUD Mitigation Jun Heo, Sieun Baek, and Hee-Sang Shim(KAERI) PDF보기 -
2026-Autumn 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.30(Fri) 09:40 105 Microstructural Evolution of Electrodeposited Cr Barrier Layers and Carbide Induced Interface Degradation of HT9 Cladding during Long Term Thermal Aging at 650 °C Hyeongwoo Min and Young Soo Yoon(Gachon Univ.),Sunghwan Yeo, Jun Hwan Kim, and Jeong Mok Oh(KAERI) PDF보기 -
2026-Autumn 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.30(Fri) 10:00 105 High-Temperature Oxidation of XM19 Stainless Steel in Air and Steam-Air: Grain Size Effect and Comparison with SS304H Stainless Steel Seungyoon Baik, Taeyun Kwon, Woohyun Lim, and Chansun Shin(Myongji Univ.), Hyung-Ha Jin(KAERI) PDF보기 -
2026-Autumn 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.30(Fri) 10:20 105 Investigation of Thermal Creep Behavior and Microstructural Degradation in modified 9Cr-2W Steel Dong-Ha Kim, Sunghwan Yeo, JunHwan Kim, and Jeong Mok Oh(KAERI) PDF보기 -
2026-Autumn 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.30(Fri) 11:00 105 Rehydration of Molten Chloride Salts and Its Impact on SS316H Corrosion for Molten Salt Reactor Applications Seol Kim, Joonha Park, and Seok Min Yoon(UST|KAERI), Hyeonwoo Kim and Sangtae Kim(HYU), Dokyu Kang, Taeho Kim, Chang Hwa Lee, and Eun-Young Choi(KAERI) PDF보기 -
2026-Autumn 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.30(Fri) 11:20 105 Electrochemical Impedance Spectroscopy and Polarization Resistance for In-Situ Corrosion Monitoring of SS316H and Hastelloy N in Molten NaCl-KCl Byeongmin Kong, Taehoon Park, Jihun Kim, and Sungyeol Choi(SNU) PDF보기 -
2026-Autumn 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.30(Fri) 11:40 105 Improving Hydration Resistance of Gd2O3 by HfO2 Doping Anissa Isnaini and Ho Jin Ryu(KAIST) PDF보기 -
2026-Autumn 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.29(Thu) 13:30 300A Development of a Machine Learning Potential and Evaluation of Diffusion behavior in UO₂ Using Molecular Dynamics Simulations Jiwoo Kim and Ho Jin Ryu(KAIST) PDF보기 -
2026-Autumn 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.29(Thu) 13:50 300A Influence of Atmospheric Environments on Spark Plasma Sintering Kinetics, and Microstructural Evolution in Inconel 718 and 316 Stainless Steel Alloys Seong Gyu Chung and Hwasung Yeom(DANE. POSTECH), Evan Willing and Noah Anderson and Kumar Sridharan(UW Madison), Omer Cakmak, Guichuan Li, and Jung Wook Cho(GIFT) PDF보기 -
2026-Autumn 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 10.29(Thu) 14:10 300A A Structural Analysis Methodology for Reactor Vessel Internals under Flow-Induced Vibration Considering Spatial Partial Correlation Chiwoong Ra, No-cheol Park, and Youngjin Park(Yonsei Univ.) PDF보기 -
Last Modified : 1998-Autumn