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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Sodium-Cooled Fast Reactor Helical Coil Steam Generator Eui Kwang Kim and Seong-O Kim(KAERI) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Preliminary Requirement for Internal Structure Configuration of 600 MWe SFR Ji-Woong Han, Jae-Hyuk Eoh, and Seong-O Kim(KAERI) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Feasibility Study on New Concept of DHRS in KALIMER-600 Kwi-Seok Ha, Hae-Young Jeong, Won-Pyo Chang, Young-Min Kwon, and Kwi-Lim Lee(KAERI) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Analysis of Core Disruptive Accidents in a Small Sodium Fast Reactor S.D. Suk and H.Y. Jeong(KAERI) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Core Design Studies for a 600 MWe Demonstration TRU Burner Reactor Hoon Song, Won Seok Park, and Sang Ji Kim(KAERI) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Improved Design for Battery Reactor Vessel Assembly Hyunng M. Son and Kune Y. Suh(SNU) Kune Y. Suh(PHILOSOPHIA) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Design Evaluation of the ABTR Internal structure on Seismic Loads S. H. Kim, G. H. Koo, and J. B. Kim(KAERI) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Ultrasonic Waveguide Sensor with a Layer-structured Plate Young-Sang Joo, Jin-Ho Bae, and Jong-Bum Kim(KAERI) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Simulations of Propagation and Radiation of Ao -mode Lamb Wave in Ultrasonic Waveguide Sensor Jin-Ho Bae, Young-Sang Joo, and Jong-Bum Kim(KAERI) Hui-Nam Rhee(SCNU) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Preliminary Evaluation of Application of Current General Design Requirements to Hydrogen Generation Nuclear Plant Changwook Huh, Young Gill Yune, Jaeho Song, and Kyun-Tae Kim(KINS) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Whole-Core Thermal Analysis of Prismatic Very High Temperature Reactor Nam-il Tak, Min-Hwan Kim, Hong-Sik Lim, Ji Su Jun, and Chang Keun Jo(KAERI) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Mixture Gas-water Loop Design to Investigate Thermal Hydraulic Performance of a PCHE In Hun Kim and Hee Cheon No(KAIST) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) High-temperature Structural Modeling on the PHE Prototype for KAERI's Helium Gas Loop Keenam Song, Y-W Kim, and S-D Hong(KAERI) H-Y Park(AD Solution) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) CFD Analysis of Hot Spot Fuel Temperature in the Control Fuel Block Assembly of a VHTR Core Min-Hwan Kim, Nam-il Tak, and Jae Man Noh(KAERI) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) A Study on the Buoyancy and Radiation Effects of the Experimental Helium Loop for VHTR Simulation Churl Yoon, Sung Deok Hong, Jae Man Noh, Yong Wan Kim, and Jong Hwa Chang(KAERI) PDF보기 -
Last Modified : 1998-Autumn