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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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 -
2008-Autumn 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) Fracture Mechanics Analysis for Structural Integrity Assessment of Reactor Pressure Vessel Under Pressurized Thermal Shock Condition Jong-Wook Kim, Gyu-Mahn Lee, and Tae-Wan Kim (KAERI) PDF보기 -
2008-Autumn 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) Fatigue Analysis of Pressurizer Spray Nozzle by 3-Dimensional Finite Element Modeling Deog Ji Kang, Tae Soon Kim, and Jae Gon Lee (KHNP) PDF보기 -
2008-Autumn 제 4 분과 : 핵연료및원자력재료(Nuclear Fuel and Materials) Study on the effects of Ni-plating Process Parameters on the Properties of Ni-deposit Joung Soo Kim, Myung Jin Kim, Dong Jin Kim, and Hong Pyo Kim (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Heat Conductor Model for the Component Thermal-Hydraulic Analysis Module, CUPID H. K. Cho, I. K. Park, H. Y. Yoon, J. Kim, and J. J. Jeong (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) MARS Code Improvement of Selection Criteria on Determining Condensation Heat Transfer Coefficient in Vertical Tube Young-Suk Bang, Ji-Han Chun, and Goon-Cherl Park (SNU) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) MARS Validation Plan and Status Ahn, Seung-hoon and Cho, Yong-jin (KINS), Chung, Bub-dong (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development Status of THALES Code Kee Yil Nahm, Jong Seon Lim, Chong Kuk Chun, Sung Kew Park, and Sung Chu Song (KNF) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Application Strategy of Direct Solution Methodology to Matrix Equations in Hydraulic Solver Package Young W. Na, C. E. Park, and Sang Y. Lee (KOPEC) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Investigation and Selection of Entrainment-Deposition Correlations for the Development of SPACE Code Lee Eo Hwak and NO Hee Cheon (KAIST), Cho Hyoung Kyu, Kim Kyung Doo, and Bae Sung-Won (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Moderator Circulation Mode of CANDU-6 Reactor Tae Kwang Eom and Jae Young Lee (HGU), Manwoong Kim (KINS) PDF보기 -
Last Modified : 1998-Autumn