학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 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 | - |
| 2024-Spring | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.10(Fri) 11:40 | 302 (3F) | The Relationship between Oxygen Composition and Lattice Parameter in a UO2-Gd2O3 System with High Gd2O3 Content | Jae Ho Yang, Dong Seok Kim, Ji-Hae Yoon, Ji-Hwan Lee, and Dong-Joo Kim(KAERI) | PDF보기 | - |
| 2024-Spring | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.10(Fri) 09:00 | 303A (3F) | Effect of Stress Distribution of Thin Disk Specimen of Rupture Disk Corrosion Test on SCC Initiation of Nickel Alloys | Sung-Woo Kim, Tae-Young Kim, and Jong-Yeon Lee(KAERI) | PDF보기 | - |
| 2024-Spring | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.10(Fri) 09:20 | 303A (3F) | Corrosion Resistance Assessment of Nickel in Molten Salt Environments | Seong Sik Hwang, Soon Hyeok Jeon, Ji Hyun Yoon , Gyeong Hoi Koo, and Sang Ji Kim(KAERI), Jeoung Han Kim and Won Chan Lee(Hanbat National Univ.) | PDF보기 | - |
| 2024-Spring | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.10(Fri) 09:40 | 303A (3F) | Predicting Fatigue Crack Growth Rate of Austenitic Stainless Steels in Water Reactors Using Machine Learning Algorithms | DAYU FAJRUL FALAAKH and Chi Bum Bahn(Pusan National Univ.), Jongweon Cho(Myongji Univ.) | PDF보기 | PPT보기 |
Last Modified : 1998-Autumn
