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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) 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 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Implementation of Turbulence Models into the CUPID Code I. K. Park, J. Kim, H. Y. Yoon, H. K. Cho, and J. J. Jeong (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Staggered Semi-implicit Finite Volume Method to Solve 3-dimensional Containment Phenomena Based on Cell and Face Porosity Soon Joon Hong, Su Hyun Hwang, Tae Young Han and Byung Chul Lee (FNC), Choong Sup Byun (KEPRI) PDF보기 -
Last Modified : 1998-Autumn