학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 11:00 | 202B (2F) | Effects of Acoustic Impedance on Spent Nuclear Fuel Ultrasonic Inspection | Kyung Gun Kim and Jin Ho Jeong(KHNP) | PDF보기 | - |
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 11:20 | 202B (2F) | Exploring the Microstructural Difference Between Circumferential Hydride and Radial Hydride in Reactor-grade Zirconium Cladding Tube | Dahyeon Woo and Youho Lee(SNU), Joo-Hee Kang(KIMS) | PDF보기 | - |
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 11:40 | 202B (2F) | Effect of Reduced Hydride Connectivity on the Mechanical Strength of Zircaloy Via Grain Growth | Sangbum Kim and Youho Lee(SNU) | PDF보기 | - |
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 12:00 | 202B (2F) | A Comparative Study on Spent Nuclear Fuels under Normal and Postulated Conditions of Transportation | Min Jeong Park, Yong Gyun Shin, and Yoon-Suk Chang(KHU) | PDF보기 | - |
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 12:20 | 202B (2F) | Electron Irradiated ZrC layer in Surrogate TRISO Fuel Particles | Sunghwan Yeo, Hyunggen Lee, Eungsun Kim, and Jun Hwan Kim(KAERI) | PDF보기 | - |
| 2023-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 09:00 | 203 (2F) | On the Wrong Use of Sodium Hydroxide as a Chemical Impurity Concentrated in Nuclear Steam Generator Crevices | Do Haeng Hur, Jeoh Han, and Soon-Hyeok Jeon(KAERI), Geun-Dong Song(FNC Tech.) | PDF보기 | - |
| 2023-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 09:20 | 203 (2F) | Atomistic Investigation of Interstitial Dislocation Loop Formation and Threshold Displacement Energy in Tantalum and Tantalum-Tungsten Alloy by Low Temperature Irradiation under Local Deformation | Mohammad Banisalman, Minkyu Park, and Mosab Banisalman(Virtual Lab Inc.) | PDF보기 | - |
| 2023-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 09:40 | 203 (2F) | Multiscale Modeling Approach to Hygroelastic Aging of Epoxy and Epoxy Nanocomposites | Seunghwa Yang and Inseok Jeon(CAU), Seonyong Kwon(Samyang Corp) | PDF보기 | - |
| 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 | - |
Last Modified : 1998-Autumn
