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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Safety Analysis on Large Partial Inlet Flow Blockage in PGSFR J. Yoo, W. P Chang, J. H. Jeong, and K. S Ha(KAERl) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) CFD Investigation for Flow Blockage Accident in a Lower Plenum J. Yoo, J. H. Jeong, W. P Chang, and K. S Ha(KAERl) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Performance Estimation of Supercritical C02 Cycle for the PG-SFR Application with Heat Sink Temperature Variation Yoonhan Ahn, Seong Kuk Cho, and Jeong Ik Lee(KAIST) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) The Self-Calibration Test of Flowmeter Installed in STELLA(Sodium Integral Effect Test Loop for Safety Simulation and Assessment) Facility Minhwan Jung and Ji-Young Jeong(KAERl) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Structural Evaluation of Reactor Support Structure for a PGSFR in a Steady State Condition In-Su Han, Chang-Gyu Park, Jong-Bum Kim, and Gyeong-Hoi Koo(KAERl) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Analyses of Design Extended Condition Events for the Prototype Gen-IV SFR Chiwoong CHOI, Taekyung Jeong, Kwilim Lee, Jaeho Jeong, and Kwiseok Ha(KAERl) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) New Fuel Pin Axial Expansion Reactivity Feedback Model in MARS-LMR Chiwoong CHOI and Kwiseok Ha(KAERl) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Three-Dimensional Transient Analysis in the Upper Plenum of MONJU with MARS-LMR Kwi-Lim Lee, Jae-Ho Jeong, and Kwi-Seok Ha(KAERl) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Numerical Analysis on the Free Fall Motion of the Control Rod Assembly for the Sodium Cooled Fast Reactor Se-Hong Oh, Choengryul Choi, and Sung-Man Son(ELSOLTEC) Jae-Yong Kim and Kyung-Ho Yoon(KAERl) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Influence of Thermal Aging on Material Strength Behavior in Grade 91 Steel Hyeong-Yeon Lee and Woo-Gon Kim(KAERl) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Investigation of C02 Recovery System Design in Supercritical Carbon Dioxide Power Cycle for Sodium-cooled Fast Reactor Min Seok Kim, Hwa-Young Jung, Yoonhan Ahn, Seong Kuk Cho, and Jeong Ik Lee(KAIST) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Preliminary Study for the Design of Mesh Region in Cold Trap Sang-Min Park, and Ji-Young Jeong(KAERl) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Design Evaluation of a Piping System in the SELFA Sodium Test Facility Seok-Kwon Son, Young-Chul Jo, Hyeong-Yeon Lee, and Ji-Young Jeong(KAERl) PDF보기 -
2015-Autumn 1E : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Evaluation of Melt Behavior with Initial Melt Velocity Under SFR Severe Accidents Hyo Heo, In Cheol Bang(UNIST), Dong Wook Jerng(CAU) PDF보기 -
2015-Autumn 1F : 원자로시스템기술 (Reactor System Technology) 10.29(Thu) 13:00 다이아몬드 (B1F) Uncertainty Analysis for OECD-NEA-UAM Benchmark Problem of TMI-1 PWR Fuel Assembly Hyuk Kwon, S. J. Kim, K.W. Seo, and D. H. Hwang(KAERl) PDF보기 -
Last Modified : 1998-Autumn