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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2008-Spring 제10분과 : 원자력 계측제어 및 자동원격-Poster(Nuclear I&C and Automatic Remote Systems) Nuclear Fuel Rod Displacement Measurement Using a Wide-area CCD Sensor JaiWan Cho and YoungSoo Choi (KAERI) Jung Cheol Shin (KNF) PDF보기 -
2008-Spring 제10분과 : 원자력 계측제어 및 자동원격-Poster(Nuclear I&C and Automatic Remote Systems) Design of Reactor Coolant Pump Seal Online Monitoring System Sang-ha An and Soonheung Chang (KAIST) Song-kyu Lee (KOPEC) PDF보기 -
2008-Spring 제10분과 : 원자력 계측제어 및 자동원격-Poster(Nuclear I&C and Automatic Remote Systems) Determination of Unidentified Leakage Using a Kalman Smoother Soek Bo Jang and Gyun young Heo (KHU) Insik Ra and Jeong-Hyun Han (ACT) Seon Woo Lee (KHNP) PDF보기 -
2008-Spring 제10분과 : 원자력 계측제어 및 자동원격-Poster(Nuclear I&C and Automatic Remote Systems) Conceptual Design of a Leak Detector Using Audio and Video Captures Bo Gyung Kim and Gyun young Heo (KHU) PDF보기 -
2008-Spring 제10분과 : 원자력 계측제어 및 자동원격-Poster(Nuclear I&C and Automatic Remote Systems) Discrimination of a Crack in the Ultrasonic Spectrum Signal of Multi Laser Beams J. S. Kim and S. H. Lee (CBNU) S. K. Park and S. H. Baik (KAERI) Y. J. Kang (CBNU) PDF보기 -
2008-Spring 제10분과 : 원자력 계측제어 및 자동원격-Poster(Nuclear I&C and Automatic Remote Systems) Application of 4-Face Fuel Visual Inspection System during Outage in Nuclear Power Plant J. C. Shin, J. I. Kim, C. B. Choi, and Y. C. Kim (KNF) C. B. Kang (KHNP) PDF보기 -
2007-Autumn 제1분과 : 원자로시스템기술(Nuclear System Technology) The Evaluation of Impact Strength of IFM Support Grid and its Experimental Verification Soobum Lee and Keenam Song (KAERI) PDF보기 -
2007-Autumn 제1분과 : 원자로시스템기술(Nuclear System Technology) Application of CASMO-3/MASTER Code System to the OPR1000 Guk Jong You, Jung Hoon Sim, and Han Gon Kim (KHNP) PDF보기 -
2007-Autumn 제1분과 : 원자로시스템기술(Nuclear System Technology) Core Design of a 1200 MWe Sodium Cooled Fast Reactor by Using Non-Fuel Rods Ki-Bog Lee, Hyung-Kook Joo, Jae-Woon Yoo, and Yeong-il Kim (KAERI) PDF보기 -
2007-Autumn 제1분과 : 원자로시스템기술(Nuclear System Technology) Comparison of Three-Dimensional Thermal-Hydraulic Characteristics Between 7-pin and 19-pin Wire-Wrapped Fuel Assemblies Wasim Raza and Kwang-Yong Kim (IHU) PDF보기 -
2007-Autumn 제1분과 : 원자로시스템기술(Nuclear System Technology) Influence of Nuclear Data Files on the Analyses of Metallic Uranium Fueled BFS Critical Assemblies Jaewoon Yoo, Yeong-Il Kim, and Hoon Song (KAERI) PDF보기 -
2007-Autumn 제1분과 : 원자로시스템기술(Nuclear System Technology) The GAMMA Code Assessment of the HTR-10 Safety Demonstration Experiments-LOFC ATWS Ji Su Jun, HongSik Lim, and Won-Jae Lee (KAERI) PDF보기 -
2007-Autumn 제1분과 : 원자로시스템기술(Nuclear System Technology) Development of a Spark Ignition Model for a CFD Analysis of the JAEA Explosion Test H. S. Kang, S. B. Kim, M. H. Kim, and W. J. Lee(KAERI) H. C. No (KAIST) PDF보기 -
2007-Autumn 제1분과 : 원자로시스템기술(Nuclear System Technology) CFD Analysis on the Prismatic Fuel Assembly of a Very High Temperature Reactor Nam-il Tak, Min-Hwan Kim, and Won-Jae Lee (KAERI) PDF보기 -
2007-Autumn 제1분과 : 원자로시스템기술(Nuclear System Technology) Thermal-Fluid Analysis of the Local Hot Core Region in a Pebble-Bed Reactor Min-Hwan Kim, Hong-Sik Lim, and Won-Jae Lee (KAERI) PDF보기 -
Last Modified : 1998-Autumn