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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Development of Aerosol Behavior Analysis Module for GAMMA+ Jun Soo Yoo, Nam il Tak, and Hong Sik Lim(KAERI) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Linearization of Valve Flow Characteristics for Steam Turbine Control Seong G. Kang and Kune Y. Suh(SNU) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Numerical Simulation of RCCS under LPCC Accident in PMR600 Using CFD Seong Hoon Kim, Namil Tak, and Min-Hwan Kim(KAERI) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Parametric Study on an Initial Cooling Performance in the KALIMER-600 Ji-Woong Han, Jae-Hyuk Eoh, Tae-ho Lee, and Seong-O Kim(KAERI) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Acoustic Leak Detection Testing Using KAERI Sodium-water Reaction Signals for a SFR Steam Generator Tae-Joon Kim, Ji-Young Jeong, Jong-Man Kim, Byung-Ho Kim, and DoHee Hahn(KAERI), Valeriy S. Yugay(SS PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Assessment of the KALIMER-600 Burner Reactor Responses to an Unprotected Overpower Transient Young-Min KWON, Hae-Young JEONG, Kwi-Seok HA, Hoon SONG, and Sang-Ji KIM(KAERI) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Design Features of the Passive Decay Heat Removal System of KALIMER-600 Jae-hyuk Eoh, Tae-ho Lee, Yong-bum Lee, and Seong-O Kim(KAERI) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Recent Research at KAERI for a Supercritical CO2 Brayton ECS for a Gen-IV SFR J.E. Cha, J.H. Eoh, S.H. Seong, and S.O. Kim(KAERI) D.E. Kim and M.H. Kim(POSTECH) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Structural Economic-improvement Design of a Large Pool Type SFR of 1200MWe Lee, Jae-Han and Park, Chang-Gyu(KAERI) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Advanced Design Concepts and R&D Activities for a Gen IV SFR Dohee Hahn(KAERI) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Wastage Characteristics of a Modified 9Cr-1Mo Steel Tube Material for a SFR SG Ji-Young Jeong, Jong-Man Kim, Tae-Joon Kim, Jong-Hyeun Choi, and Byung-Ho Kim(KAERI), Nam-Cook Park( PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Design Improvements for a 1,200MWe SFR Breakeven Core Hyung-Kook Joo, Jin-Wook Jang, Jae-Woon Yoo, and Yeong-Il Kim(KAERI) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Concept Synopsis of the AMBIDEXTER Nuclear Energy Complex Se Kee Oh, Young Joon Lee, Tae Kyu Ham, Myung Hwan Seo, Sung Taek Hong, and Tae An Kwon(AJOU) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) Sustainomics of the AMBIDEXTER-NEC Fuel Cycle and Management Se Kee Oh, Young Joon Lee, Tae Kyu Ham, Myung Hwan Seo, Sung Taek Hong, and Tae An Kwon(AJOU) PDF보기 -
2009-Spring 제 1 분과 원자로시스템기술(Reactor System Technology) A Benchmark CFD Calculation for a Cross Flow between Fuel Blocks of a Prismatic VHTR Nam-il Tak, Min-Hwan Kim, and Won Jae Lee(KAERI) PDF보기 -
Last Modified : 1998-Autumn