학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2010-Spring | 제 3 분과 : 방사성폐기물관리(Radioactive Waste Management) | Redox Behavior of Fe +/Fe + Redox Couple by Absorption Spectroscopy and Measurement | J. Y. Oh, S. Park and J. I. Yun(KAIST) | PDF보기 | - | ||
| 2010-Spring | 제 3 분과 : 방사성폐기물관리(Radioactive Waste Management) | Spectroscopic Speciation of Iron Using Complexing Agents | S. Park, J. Y. Oh, and J. I. Yun(KAIST) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | PWSCC of Alloy 600 Components and its Countermeasures in PWRs | Seong Sik Hwang, Sung Woo Kim, Jangyul Park, and Hong Pyo Kim(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | PWSCC Crack Tip Observation of Alloy 600 | Yun Soo Lim, Hong Pyo Kim, Hai Dong Cho, and Han Hee Lee(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Relationship between Residual Stress of Dissimilar Metal Welding and Stress Corrosion Cracking of Alloy 600 Nozzle in Bottom Mounted Instrumentation of PWR | Sung-Woo Kim and Hong-Pyo Kim(KAERI) Jae-Uk Jeong(SKKU) Yoon-Suk Chang(KHU) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Study on the Fabrication of the Stress Corrosion Crack by Vapor Pressure in the Alloy 600 Pipe | Jae-Seong Kim, Ju-seon An, Woong-Ki Hwang, and Bo-Young Lee(KAU) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | TEM Study on the Proton Irradiated Type 316 Stainless Steel | Yun Soo Lim, Seong Sik Hwang, Hong Pyo Kim, and Hai Dong Cho(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Creep and Creep Crack Growth Behaviors for SMAW Weldments of Gr. 91 Steel | Woo-Gon Kim, Song-Nan Yin, Ji-Yeon Park, Sung-Deok Hong, and Yong-Wan Kim(KAERI) Jae-Young Park(PKNU | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Characterization of Strength and Fracture Toughness of Nuclear Graphite Using Subsize Specimen | Ji Hyun Yoon(KAERI) Thak Sang Byun, Joe. P. Strizak, and Lance. L. Snead(ORNL) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Effects of Thermal Conductivity Degradation of UO Fuel on Safety Margins | Joosuk Lee, Wonjoon Nah, Sungsik Kang, and Swengwoong Woo(KINS) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Analysis of Breakaway Oxidation Behavior of Zr Claddings after LOCA Simulation Test | Hyun-Gil Kim, Il-Hyun Kim, Byung-Kwan Choi, Jeong-Yong Park, and Yong-Hwan Jeong(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Development of Measurement Technique for Thermal Diffusivity of Oxide Fuel in HotLaboratory | Heemoon Kim, Dae-Gyu Park, Sang-Ho Na, Chang-Je Park, Kweon Ho Kang, Byung Ok Yoo, Sang Youl Baek, S | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Fabrication of Sintered Annular Fuel Pellet | Young Woo Rhee, Dong Joo Kim, Jong Hun Kim, Jae Ho Yang, Keon Sik Kim, Ki Won Kang, and Kun Woo Song | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Effect of Fluorine on the Breakaway Oxidation Properties of Zr-alloy | S. Y. Park, D. J. Park, J. Y. Park, and Y. H. Jeong(KAERI) K. W. Lee and S. I. Hong(CNU) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Microstructural Analysis and XPS Investigation of Nodular Oxides Formed on Zricaloy-4 | Dong Jun Park, Jeong Yong Park, Byoung Kwon Choi, and Yong Hwan Jeong(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
