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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2005-Autumn 제1분과 : 원자로기술 The Thermal-hydraulic Performance of PCHE in an Air Test Loop Sung Chu Song and Hee Cheon NO (KAIST) Cheol Shin Lee (KOPEC) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 CFD Analysis of the Fuel Temperature in High Temperature Gas-cooled Reactors W. K. In, T. H. Chun, W. J. Lee, and J. H. Chang (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Modeling of a Bunsen Reaction with a Chemical Process Simulator J. H. Kim, Y. J. Shin, J. H. Chang, and J. K. Park (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 The Effect of the Inner Pressure Induced by Fission Gas on the SiC Layer Integrity Hyedong Jeong, Yong Hoon Jeong, and Soon Heung Chang (KAIST) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 A Preliminary Neutral Framework for the Accident Sequence Evaluation for a Hydrogen Conversion Reactor Seok-Jung Han and Joon-Eon Yang (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Cycle Analysis of the Recompression Supercritical CO2 Brayton Cycle Eui-Kwang Kim, Kwi-Seok Ha, Won-Pyo Chang, and Yong-Bum Lee (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Evaluation of SDS1 Depth for Pressure Tube Ruputure in Wolsong-1 NPP Kim YunHo and Choi Hoon (KEPRI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 REFORM Optimization to Improve ROPT Margins for Wolsong-1 Park Dong Hwan (GNEST) Lee Eun Ki, Kim Yun Ho, and Kim Yong Bae (KEPRI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Velocity of Delayed Hydride Cracking with Stress Intensity Factor in Zr-2.5Nb Pressure Tube Kang Soo Kim, Young Suk Kim, Yong Moo Cheong, Sang Bok Ahn, and Kyoung Soo Im (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 A Conceptual Core Design of a High Temperature Reactor Cooled by Super Critical Water Kang-Mok Bae, Hyung-Kook Joo, Hyun-Chul Lee, Jae-Man-Noh, and Yoon-Yong Bae (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Single Phase Turbulent Mixing in Square Rod Arrays at Highly Turbulent Condition Hae-yong Jeong, Kwi-seok Ha, Young-min Kwon, Sun Heo, Won-pyo Chang, and Yong-bum Lee (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Development of a Multidimensional Analysis Methodology for a Sodium-water Reaction in a SFR Steam Generator Seyun Kim, Jae-Hyuk Eoh, Won-Dae Jeon, and Seong-O Kim (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Structural Integrity Evaluation of the KALIMER-600 Reactor Core Support Structure Chang-Gyu Park, Jong-Bum Kim, and Jae-Han Lee (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Mechanical Design Features of the KALIMER-600 Sodium-cooled Reactor Jae-Han LEE, Chang-Gyu Park, and Jong-Bum Kim (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Under-sodium Inspection Techniques for Reactor Internals of KALIMER-600 Using Ultrasonic Waveguide Sensor Young-Sang Joo, Seok-Hoon Kim, and Jae-Han Lee (KAERI) PDF보기 -
Last Modified : 1998-Autumn