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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Overall Instrumentations for the ATLAS Integral Effect Test Program B. J. Yun, K. H. Kang, B. D. Kim, and W. P. Baek (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Air-water Multidimensional Flow Characteristics on Vertical Flat Wall Won J. Kim and Kune Y. Suh (SNU) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Scalability Analysis of Large Loss-of - coolantaccident at 8% Power Level for APR1400 and ATLAS Soon Joon Hong and Byung Chul Lee (FNC Tech) Heedo Lee (KOPEC) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Comparative Analysis of ATWS for OPR1000 by Using RETRAN-3D and CESEC-III Codes Sang IL Lee, Shin Whan Kim, and Eun Kee Kim (KOPEC) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Frequency Characteristics of Thermal Fluctuations Induced by Triple Jets Ho-Yun Nam, Min-Joon Kim, Jong-Man Kim, and Byoung-Hae Choi (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Assessment of Turbulence Models and Its Application to Pebble Bed Reactor J. J. Lee, S. K. Kang, S. J. Yoon, and G. C. Park (SNU) PDF보기 -
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 -
Last Modified : 1998-Autumn