학술발표회 논문집
Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
---|---|---|---|---|---|---|---|
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | Evaluation of Finite Pulse Time Effects Using Azumi Method | Daegyu Park, Heemoon Kim, and Wooseok Ryu (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | Acquisition/Diversion Pathway Analysis of the DUPIC Fuel Cycle for the Assessment of Proliferation Resistance | Hong-Lae Chang and Won Il Ko (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | A Preliminary Economic Evaluation for Advanced CANDU-6 Fuels | Jong Yeob Jung and Joo Hwan Park (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | Water Loop System Development for IASCC Tests at High Temperature | Han-Hee Lee, Won-Sam Kim, Seung-Mo Hong, and Seong Sik Hwang (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | Effect of Additives on a Stress Corrosion Cracking of Alloy 600 in a PbO-added Neutral Solution | Mi-Ae Kim, Dong Jin kim, Joung Soo Kim, and Hong Pyo Kim (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | A Review on the OECD Halden Reactor Project for an Irradiation Assisted Stress Corrosion Crackin | Won Sam Kim, Han-Hee Lee, Seung Mo Hong, and Seong Sik Hwang (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | Comparison of a Leak Behavior of an ID/ODSCC Developed on SG Tubes | ChanNam Gung, SeongSik Hwang, Jangyul Park, ManKyo Jung, and HongPyo Kim (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | IASCC Experiment Methods Using Proton Irradiated Stainless Steel Specimens | Seung Mo Hong, Han-Hee Lee, Won-Sam Kim, and Seong-Sik Hwang (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | A Study on the Passive Film of Alloy 600 and Alloy 690 Formed in the High Temperature Aqueous Solution with Additives | Hyuk-Chul Kwon, Dong-Jin Kim, and Hong Pyo Kim (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | Electrochemical Corrosion Behavior of Alloy 600 in Chloride-Sulfate Solutions | Do Haeng Hur, Myung Sik Choi, Jung Ho Han, and Deok Hyun Lee (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | Non Destructive Measurement of the Setup Angle Between the Penetration Nozzle and the Pressure Vessel | Deok Hyun Lee, Myung Sik Choi, Do Haeng Hur, Kyung Mo Kim, and Jung Ho Han (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | PWSCC Growth Characteristic of a High Temperature Mill Annealed Alloy 600 Tube for a Korean Standard Nuclear Power Plant (KSNP) | SungSoo Kim, Joung-Soo Kim, Seong Sik Hwang, and Hong-Pyo Kim (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | Comparison of Crystallographic Texture of Domestic Zirconium Alloy Tubes by Using X-ray Diffraction Method | J. J. Lee, H. J. Cho, Y. W. Moon, J. M. Jang, N. I. Baik, and Y. Choi (SMU) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | Analysis of Integrity for Baffle/Former Bolt of Reactor Internal | Dae Whan Kim and Seong Sik Hwang (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) | Evaluation of the Neutron Fluence at a Baffle-Former Zone in an Operating Reactor | S. L. Lee, C. S. Yoo, and S. S. Hwang (KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn