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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2011-Autumn 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Remote Operation) Detection of Wall-Thinned Defects Using IR Thermography Ju Hyun Kim, Young Gyu No, Soon Ho Park, Man Gyun Na, Jin Weon Kim, Hyun Chul lung, and Kyeong Suk K PDF보기 -
2011-Autumn 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Remote Operation) A Study on Evaluation of Activation Energy of EPR through Volume Electrical Resistivity In Yong Kim and Cheol Soo Goo(KINS) Jung Hoon Lee and Yong Deok Shin(WKU) PDF보기 -
2011-Autumn 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Remote Operation) A Cyber Security Risk Assessment Procedure for Digital I&C Systems in NPPs J. G. Song, J. W. Lee, C. K. Lee, K. C. Kwon, and D. Y. Lee(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) LBE-cooled Natural-circulation Small Modular Reactor without on-site Refueling Jae Hyun Cho, Sungyeol Choi, Moo-Hoon Bae, Jun Lim, Dina Puspitarini, Ji Hoon Jeun, Han-Gyu Joo, and PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Analysis of the Nonlinear Density Wave Two-phase Instability in a Steam Generator of 600MWe Liquid Metal Reactor Seok-Ki Choi and Seong-O Kim(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Core Thermal-hydraulic Design of a Sodium Cooled Fast Reactor for the U/TRU Fuel Modification Sun Rock Choi, Chungho Cho, Young-Gyun Kim, Hoon Song, Wonseok Park, and Sang-Ji Kim(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Component Modeling Description for COMMIX Analysis of 600MWe Sodium-cooled Fast Reactor Ji-Woong Han, Jae-Hyuk Eoh, and Seong-O Kim(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Pre-test CFD Analysis of a Bypass Flow Experiment for VHTR Simulation Churl Yoon and Min-Hwan Kim(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Preliminary Calculations of Bypass Flow Distribution in a Multi-block Air Test Min-Hwan Kim and Nam-il Tak(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Pressure Drop of Hybrid Heat Exchanger for SO3 Decomposition Chan Soo Kim, Dong-Un Seo, Tae-Ho Yoo, Sung-Deok Hong, and YongWan Kim(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) CFD Analysis for Predicting Flow Resistance of the Cross Flow Gap in Prismatic VHTR Core Jeong-Hun Lee, Su-Jong Yoon, and Goon-Cherl Park(SNU) Jong Woon Park(DU) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Design Optimization of A PCHE Using RSA Model Sang-Moon Lee and Kwang-Yong Kim(INHA Univ.,) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Parametric Study on an Outlet Plenum of the PBMR Jae-Woo Ju, Sang-Moon Lee, and Kwang-Yong Kim(INHA Univ.,) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) High-temperature Structural Analysis Modeling on the Small-scale PCHE Prototype Keenam Song, S-D Hong, and H-Y Lee(KAERI) H-Y. Park(AD solution) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Simulation of a Heat Transfer between Gases in SO3 Decomposer J. H. Kim, T. H. Lee, K. Y. Lee, and Y. W. Kim(KAERI) PDF보기 -
Last Modified : 1998-Autumn