학술발표회 논문집
Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
---|---|---|---|---|---|---|---|
2023-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 10:00 | 203 (2F) | Formation of Nanotwins in Proton-Irradiated Austenitic 316 Stainless Steel | Yun Soo Lim, Dong Jin Kim, Sung Sik Hwang, Sung Woo Kim, Min Jae Choi, and Sung Hwan Cho(KAERI) | PDF보기 | - |
2023-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 10:20 | 203 (2F) | Enhancing the Accuracy of Embrittlement Trend Curves for Nuclear Power Plants through Group Bias Estimation with a Multilevel Model | Gyeong-Geun Lee, Bong-Sang Lee, Min-Chul Kim, and Jong-Min Kim(KAERI) | PDF보기 | - |
2023-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 11:00 | 203 (2F) | Factors for IASCC Initiation of Reactor Internal Materials of PWRs | Seong Sik Hwang, Min Jae Choi, Sung Woo Kim, and Dong Jin Kim(KAERI) | PDF보기 | PPT보기 |
2023-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 11:20 | 203 (2F) | Effects of Peening on Material Properties and Primary Water Stress Corrosion Cracking Behavior of Alloy 600 | Baosheng Bai, Sungyu Kim, Joonho Moon, and Chi Bum Bahn(PNU), Wongeun Yi(Doosan Enerbility Co., Ltd.), Eunsub Yun(KHNP) | PDF보기 | - |
2023-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 11:40 | 203 (2F) | Effect of Residual Stress on Oxidation Behavior of Stainless Steel 304L in Simulated Secondary Water Environment of PWR | Kyeongtae Park, Junhyuk Ham, and Ji Hyun Kim(UNIST), Seung Chang Yoo(KINS) | PDF보기 | - |
2023-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 12:00 | 203 (2F) | Improvement Flow Accelerated Corrosion resistance of Carbon steel by Chromium electroplating and Plasma Nitriding | Dong-Ha Kim, Jeong Mok Oh, Sunghwan Yeo, Sung Ho Kim, and Jun Hwan Kim(KAERI) | PDF보기 | - |
2023-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 12:20 | 203 (2F) | 550℃ Liquid Lead-Bismuth Eutectic Corrosion of Direct Energy Deposited AFA Steel Laser Cladding | Taeyong Kim, Byeongju Kim, and Ji Hyun Kim(UNIST), Gidong Kim(KIMS) | PDF보기 | - |
2023-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 13:30 | 202B (2F) | Creep Assessment for High-Temperature Nuclear Materials | Woo Gon Kim, Youngjin Roh, and Seonhwa Kim(KETG) | PDF보기 | - |
2023-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 14:00 | 202B (2F) | Corrosion of Candidate Structural Materials in a Flowing NaCl-MgCl2 Salt Environment | Taeho Kim, Dong Jun Shin, Su Jeong Heo, Dalsung Yoon, Eun-Young Choi, and Chang Hwa Lee(KAERI) | PDF보기 | - |
2023-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 14:20 | 202B (2F) | Corrosion Study of Hastelloy N with Electrochemical Impedance Spectroscopy in NaCl-MgCl2-NiCl2 Systems | Jun Woo Park and Jong-Il Yun(KAIST) | PDF보기 | - |
2023-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 15:00 | 202B (2F) | Effect of Metal-assisted Chemical Purification on Corrosion in Molten Chloride Salts of Stainless Steel | Hyeon-Geun Lee, Jung-Min Kim, Taeho Kim, and Daejong Kim(KAERI) | PDF보기 | - |
2023-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 15:20 | 202B (2F) | Corrosion Behaviors of 3-D Printed Ni-based Alloy in Molten NaCl-MgCl₂ Salt | Younghwan Jeon, Hyeongjin Byeon, Kiwon Kang, and Jaeyeong Park(UNIST) | PDF보기 | - |
2023-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 13:40 | 203 (2F) | PM-HIP Manufacturing Method for Nuclear Reactor Components | Jinsung Jang, Seung Ho Joo, Min-Chul Kim, and Jong Min Kim(KAERI) | PDF보기 | PPT보기 |
2023-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 14:00 | 203 (2F) | Effect of Scan Strategy of SA508 Gr.3 Constituting Reactor Pressure Vessel on Mechanical Properties in Directed Energy Deposition | Wonjong Jeong and Ho Jin Ryu(KAIST), Young-Bum Chun, Suk Hoon Kang, Chang Kyu Rhee, and Min-Chul Kim(KAERI), Chang Hyoung Yoo, Seongjin Yoo, and Hongmul Kim(HANA amt) | PDF보기 | - |
2023-Spring | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 14:20 | 203 (2F) | Evaluation of Thermal Ageing Behavior of an Alumina-forming Duplex Stainless Steel (ADSS) Alloy at 375℃ and 400℃ | Chaewon Kim, Sumin Kim, and Changheui Jang(KAIST) | PDF보기 | - |
Last Modified : 1998-Autumn