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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2012-Spring 제 10 분과 : 원자력계측제어 및 자동원격(Nuclear l&C and Remote Control) A Study on UAE Cultural Effects on Nuclear Power Plant (NPP) Operation Inseok Jang, Poonghyun Seong, and Hyungook Kang(KAIST) PDF보기 -
2012-Spring 제 10 분과 : 원자력계측제어 및 자동원격(Nuclear l&C and Remote Control) A Human Reliability Evaluation Tool for Main Control Rooms in Nuclear Power Plants Seung Jun Lee, Jaewhan Kim, and Wondae Jung(KAERI) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Multi-objective Optimization of A PCHE Channels Sang-Moon Lee and Kwang-Yong Kim(INHA Univ.) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Shape Optimization of Outlet Plenum of the PBMR Jae-Woo Ju, Sang-Moon Lee, and Kwang-Yong Kim(INHA Univ.) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Air-cooled RCCS Failure Mode and Effect Analysis for a VHTR Hong-Sik Lim and Nam-il Tak(KAERI) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Introduction of Facility for Testing of Electromagnetic Flow Rate Transducer in KAERI Tae-Joon Kim, In-Koo Hwang, Ji-Young Jeong, Jong-Man Kim, Yong-Bum Lee, and Yeong-il Kim(KAERI) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Design and Evaluation of the Helical-coil Sodium-to-Air Heat Exchanger of STELLA-1 Jae-Hyuk EOH, Hyeong-Yeon LEE, and Yong-Bum LEE(KAERI) Byeong-Gap KIM(CD-adapco Korea) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Calculation Model for the Thermal Insulation of Pipes and Tanks Dongsup So and Yong Bum Lee(KAERI) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Thermal-hydraulic Analysis of Reactor Hot Pool of Sodium-cooled Fast Reactor Tae-Ho Lee, Jae-Hyuk Eoh, Ji-Woong Han, and Seong-O Kim(KAERI) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Isothermal Global Flow Investigation of the KALIMER-600 Water Scaled Model J. E. Cha, S. H. Lim, and S. O. Kim(KAERI) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) MARS-LMR Modeling for the Post-test Analysis of Phenix End-of-Life Natural Circulation Hae-Yong Jeong, Kwi-Seok Ha, Won-Pyo Chang, and Kwi-Lim Lee(KAERI) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Analysis of Decay Heat Removal by Natural Convection in LMR with a Combined Steam Generator Eui-Kwang Kim, Jae-Hyuk Eoh, Ji-Woong Han, and Tae-Ho Lee(KAERI) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Evaluation of Helium Release for Am-bearing Metal Fuel up to 10 at.% Burnup Byoung Oon LEE, Jin Sik CHEON, Jun Hwan KIM, and Chan Bock LEE(KAERI) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Structural Analysis of a Reservoir Tank in the STELLA-1 Test Facility S. H. Kim, Y. B. Lee, and H. Y. Lee(KAERI) H. Y. Park(AD-Solution Co., Ltd.) PDF보기 -
2011-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Evaluation of Internal Structure Effects on Thermal-hydraulic Behavior in a Sodiumcooled Pool Type Reactor Ji-Woong Han, Tae-Ho Lee, and Seong-O Kim(KAERI) PDF보기 -
Last Modified : 1998-Autumn