학술발표회 논문집 (ISSN: 3140-1864)
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2016-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Effect of Thickness on Oxidation Behavior of Cr-coated Zircaloy-4 using Arc Ion Plating | Eui-Jung Kim, Jung-Hwan Park, Hyun-Gil Kim, Yang-Il Jung, Dong-Jun Park, and Sun-Jin Kim(KAERI) | PDF보기 | - |
| 2016-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Fatigue characteristics of ODS surface treated Zircaloy-4 | Sun-Han Kim, Yang-Il Jung, Dong-Jun Park, Jung-Hwan Park, Hyun-Gil Kim, Jae-Ho Yang, and Yang-Hyun Koo(KAERI) | PDF보기 | - |
| 2016-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | High Temperature Oxidation Behavior of Zirconium Alloy with Nanostructured Oxide Layer in Air Environment | Yang Jeong Park, Jung Woo Kim, Ji Won Park, and Sung Oh Cho(KAIST) | PDF보기 | - |
| 2016-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Sensitivity Analysis of the Oxidation Rate of Cladding for the BDBA Condition using SCDAP/RELAP5 | Changhwan Shin, Tae-Hyun Chun, Wang-Kee In, and Yang-Hyun Koo(KAERI) | PDF보기 | - |
| 2016-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Evaluation of advanced zirconium alloy developed by KEPCO NF | Chung-yong Lee, Sung-yong Lee, Jea-young Lim, Dae-gyun Ko, Yoon-ho Kim, and Yong-kyoon Mok(KEPCO NF) | PDF보기 | - |
| 2016-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Corrosion and Oxide Properties of HANA-6 Alloy in Simulated PWR Primary Water | Hun Jang, Jea Young Lim, Chung Yong Lee, Sung Yong Lee, and Yong Kyoon Mok(KEPCO NF) | PDF보기 | - |
| 2016-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Qualitative analysis on hydrogen release in oxidation tests of Zry-4 in steam/N2 mixture at 850C and 1100C | Joonyoung Sung and Jaeyoung Lee(HGU), Sanggil Park(ACT Co., Ltd.) | PDF보기 | - |
| 2016-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | High-temperature steam-oxidation behavior of Zr-1Nb-1Sn-0.1Fe cladding tube at temperatures of 800-1000¨¬C | Cheol Min Lee, Tae Won Cheo, Gwan Yoon Jeong, Mi Jin Kim, Ji-Hyeon Kim, Hee-Jae Lee, and Dong-Seong Sohn(UNIST), Yong-Kyoon Mok(KEPCO NF) | PDF보기 | - |
| 2016-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | The Effect of Peak Temperatures and Hoop Stresses on Hydride Reorientations of Zirconium Alloy Cladding Tubes under Interim Dry Storage Condition | Hyun-Jin Cha, Ki-Nam Jang, and Kyu-Tae Kim(DU) | PDF보기 | - |
| 2016-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Spent Fuel Behaviors under Loss of Cooling/Coolant Accident in A Spent Fuel Pool | Sun-Ki Kim, Je-Geon Bang, Tae-Hyun Chun, Dae-Ho Kim, and Ik-Sung Lim(KAERI) | PDF보기 | - |
| 2016-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Effects of Hydride Rim on Ductility of Zircaloy-4 | So-Young Kang, Ho-A Kim, and Yong-Soo Kim(HYU), Ju-Seong Kim(KAERI) | PDF보기 | - |
| 2016-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Development of Fuel Assembly Finite Element Model for Spent Fuel Drop Analysis | Youngik Yoo, Namgyu Park, Seongki Lee, Kyongbo Eom, and Jongsung Yoo(KEPCO NF) | PDF보기 | - |
| 2016-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Development of Silicide Coating on Molybdenum Alloy Cladding | Woojin Lim and Hojin Ryu(KAIST), Hyun-Gil Kim and Jeong-Yong Park(KAERI) | PDF보기 | - |
| 2016-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Post-irradiation Microstructure and Dimensional Change of A3-3 Graphite Matrix Compacts for HTGR Fuel | Sunghwan Yeo, Moon Sung Cho, and Young-Woo Lee(KAERI) | PDF보기 | - |
| 2016-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Structual Analysis of the Nuclear Test rig Using 1-Way Fluid-Structural Coupled Analysis | Tae-Ho Yang, Jintae Hong, Sung-Ho Ahn, Chang-Young Joung, Sung-Ho Heo, and Seo-Yun Jang(KAERI), Kon-Whi Yeon(CNU) | PDF보기 | - |
Last Modified : 1998-Autumn
