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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Experimental Study on Size Effect of Siphon-breaking Hole in the Real-scaled Reactor Pool Soon Ho Kang, Ho Seon Ahn, Ji Min Kim, and Moo Hwan Kim(POSTECH) Kwon-Yeong Lee, Kyoungwoo Seo, and PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Prediction Model Development for Siphon Break Phenomena in a Research Reactor Kwon-Yeong Lee, Kyoungwoo Seo, Dae Young Chi, and Juhyeon Yoon(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Design Concept of Fluid System for 600MWe Grade SFR S.O. Kim, T.H.Lee, J.H. Eoh, S.K. Choi, E.K. Kim, J.W. Han, Y.I.Kim, and Dohee.Hahn(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Conceptual Design of a Helical Steam Generator with 750 MWt for an SFR Ho-Yun Nam, Jong-Bum Kim, Yong-Bum Lee, and Ji-Young Jeong(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Review of the Conceptual Design for In-vessel Fuel Handling Machines in SFR S. H. Kim and G. H. Koo(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) The Effect of Ni Nano Particles on the Chemical Activity of Liquid Sodium Gunyeop Park, Soo Jae Kim, Ho Seon Ahn, and Moo Hwan Kim(POSTECH) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Conceptual Design of Fuel Building of SFR Demonstration Reactor Developed in KAERI Lee. Jae-Han, Kim. Jong-Bum, and Koo. Gyeong-Hoi(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Development of Under-sodium Visualization Program for In-service Inspection of In-vessel Structures in a Sodium-cooled Fast Reactor Young-Sang Joo, Jin-Ho Bae, Chang-Gyu Park, and Jong-Bum Kim(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Derivation of the Scaling Criteria for a Small Scale CANDU Moderator Test Facility Bo Wook Rhee and Hyoung Tae Kim(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Numerical Study of Thermal-hydraulics in CANDU-typed Moderator Jae Ryong Lee, Han Young Yoon, and Hyoung Tae Kim(KAERI) Jae Jun Jeong(PNU) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Numerical Analysis of CANDU-6 Moderator System Using Open FOAM Se-Myong Chang(KNU) Hyoung Tae Kim(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) A Simple Fully Passive Safety Option for SMART SBLOCA Won Jae Lee(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Design Assessment and Transient Simulation of an Integral Reactor, REX-10, Using TAPINS Code Yeon-Gun Lee and Goon-Cherl Park(SNU) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) A Scaling Study of the Natural Circulation Flow of the Ex-vessell Core Catcher Cooling System of a 1400 MWe PWR for Designing a Scale-down Test Facility Bo.W. Rhee, K.S. Ha, R.J. Park, and J.H. Song(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Analysis of Combined Ocean Thermal Energy Conversion Using Waste Heat from NPPs Hyeonmin Kim, Jeong-tae Cho, and Gyunyoung Heo(KHU) Hoon Jung(KEPCO RI) PDF보기 -
Last Modified : 1998-Autumn