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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2005-Autumn 제5분과 : 원자력안전 - 중대사고 A Comparative Study Between a SGTR and a SG Module Pipe Break Accident of the Integral Type Reactor H. K. Kim, Y. J. Chung, G. H. Lee, H. C. Kim, and S. Q. Zee (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Heat Transfer Enhancement of Nanofluid in Natural Convection of an Enclosure Heated from Below In Cheol Bang, Eung Soo Kim, and Soon Heung Chang (KAIST) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Design of Graph Analysis Model to Support Decision Making Sang-Ha An, Sung-Jin Lee, and Soon-Heung Chang (KAIST) Sung Ho Kim and Tae Woon Kim (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 CHF Characteristics of R-134a Flowing Upward in an Annulus Geometry Kwi Lim Lee and Soon Heung Chang (KAIST) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Thermal Hydraulic Analysis of the MEGAPIE Target Under Beam Wandering Chungho Cho, Nam-il Tak, and Tae Yung Song (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Steady State Analysis of VISTA with TASS/SMR Dong Ju Jang, Yong Won Choi, Chang Hwan Park, and Un Chul Lee (SNU) Young Dong Hwang, Kyu Hyung Lee, PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Development of a Safety Analysis Code for a Supercritical Water Cooled Reactor (SCWR) Han Young Yoon, Soo Hyung Kim, Hee Cheol Kim, and Yoon Yeong Bae (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 An Experimental Study on the Factors for the Performance of a Shutoff Unit in the Half-core Test Loop of HANARO Kyoung-Rean Kim and Yeong Garp Cho (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Instability in Liquid Zone Control System of CANDU Reactor Joon-Suk Ji (KAERI) Sang-Nyung Kim (KHU) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Refrigerator Control Methods and Heat Exchanger Operating Condition for the CNS Jungwoon Choi, Bong Soo Kim, Young-ki Kim, Kyehong Lee, and Hark Rho Kim (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Two Dimensional CFD Analyses on the Heat Transfer for a Supercritical Pressure CO2 Bong Hyun Cho, Young In Kim, and Yoon Yeong Bae (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Flow Behavior Analysis of the Inlet Plenum with Narrow Type Flow-skirt Using CFD Code Jong-hark Park, Hee-taek Chae, Cheol Park, Heon-il Kim, and Jun-hong Kim (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Development of a Detailed Sub-channel Model for the Safety Analysis of Liquid Sodium-cooled Reactor S. Heo, H. Y.Jeong, Y. M. Kwon, and D. H. Hahn (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Review of Thermal-chemical Experiments for a CANDU Fuel Channel Hyoung Tae Kim, Bo Wook Rhee, and Joo Hwan Park (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 A CFD Analysis of the Coolant Flow Characteristics in the HANARO Gee Y. Han, Heonil Kim, and Byung J. Jun (KAERI) PDF보기 -
Last Modified : 1998-Autumn