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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Design of Helium Brayton Cycle for Small Modular High Temperature Gas cooled Reactor Ahn. Yoonhan, Lee. Jekyoung, and Lee. Jeong Ik(KAIST) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Porosity of Nuclear Gade Graphite Eung-Seon Kim, Ji-Seon Song, Sung-Deok Hong, and Yong-Wan Kim(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Simulation of Bunsen Reaction with Electro-dialysis for Efficient Phase Separation Jun Kyu Park, Shripad T. Revankar, and Jae Sung Lee(POSTECH) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Whole Core Thermal-hydraulic Design of a Sodium Cooled Fast Reactor Considering the Gamma Energy Transport Sun Rock Choi, Min-Ho Back, Wonseok Park, and Sang-Ji Kim(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Safety Evaluation of UCFR-1000 MWe with MATRA-LMR Han Seo, Sarah Kang, and In Cheol Bang(UNIST) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Determination of the Pipe Diameter and Length of a Sodium Experimental Installation for Single Phase Natural Convection Simulations Dongsup So and Yong Bum Lee(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Natural Circulation Test of the KALIMER-600 Water Scaled Model JaeEun Cha and SeongO Kim(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) A Safety Function Evaluation of the Advanced Sodium-cooled Fast Reactor in a Loss of Heat Sink Accident Kwi Lim Lee, Kwi Seok Ha, Hae Yong Jeong, Won Pyo Chang, Seok Hun Kang, and ChiWoong Choi(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Evaluation of Flow-guide Effects in a Sodium-cooled Pool Type Reactor Ji-Woong Han, Jae-Hyuk Eoh, Seong-O Kim, and Tae-Ho Lee(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Multi-dimensional Approach of MARS-LMR for the Analysis of Phenix End-of-Life Natural Circulation Test Hae-Yong Jeong, Kwi-Seok Ha, Won-Pyo Chang, and Kwi-Lim Lee(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Simulation of Phenix EOL Asymmetric Test Kwi-Seok Ha, Kwi-Lim Lee, Chi-Woong Choi, Seok-Hun Kang, Won-Pyo Chang, and Hae-Yong Jeong(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Evaluation of Pressure Loss and Heat Transfer Correlations for Design of the IntermediateHeat Exchanger in a Sodium Cooled Fast Reactor Seok-Ki Choi, Seong-O Kim, and Tae-Ho Lee(KAERI) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) GUI Program for the Calculation of Physicochemical Properties in VHTR-based SI Process Youngjun Lee, Jiwoon Chang, Youngjoon Shin, Taehoon Lee, Kiyoung Lee, and Yongwan Kim(KAERI) Jonghye PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) High-temperature Elastic Structural Analysis on a Small-scale PHE Prototype Keenam Song and S-D Hong(KAERI) H-Y Park(AD solution) PDF보기 -
2012-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Evaluation of NGNP Design Certification Boundaries Changwook HUH and Namduk SUH(KINS) PDF보기 -
Last Modified : 1998-Autumn