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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Safety Evaluation of Pre-Conceptual Designs of Advanced Burner Reactors Young-Min KWON, Chang-Gyu PARK, Chung-Ho CHO, Hoon SONG, Eui-Kwang KIM, and Sang-Ji KIM(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Structural Design Comparison of Sodium-cooled Fast Reactors Developed in KAERI Lee, Jae-Han, Park, Chang-Gyu, and Kim, Jong-Bum(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) The Design of the Annular Linear Induction EM Pump with a Sodium Flowrate of 35 kg/sec Hee Reyoung Kim, Tae Ho Lee, and Yong Bum Lee(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Performance Tests of Ultrasonic Waveguide Sensor Module for Under-Sodium Visualization of a Sodium-cooled Fast Reactor Young-Sang Joo, Jin-Ho Bae, Chang-Gyu Park, and Jong-Bum Kim(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Development of a Unit-Cell Based Multi-dimensional Heat Conduction Model for a Prismatic Fuel Block Nam-il Tak, Min-Hwan Kim, and Hong-Sik Lim(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) CFD Validation with a Multi-Block Experiment to Evaluate the Core Bypass Flow in VHTR Su-Jong Yoon, Jeong-Hun Lee, and Goon-Cherl Park(SNU) Min-Hwan Kim(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Thermal Stress Assessment of Graphite Fuel Blocks in a Very High Temperature Reactor Core Ji-Ho Kang, Nam-il Tak, and Min-Hwan Kim(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Overpressure Predictions by the MEM and the Baker-strehlow-Tang Blast Curves for the SRI H Explosion Test in the Open Space H.S.Kang, S.B.Kim, and M.H.Kim(KAERI) H.C.No(KAIST) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) An Analysis of the Secondary Cooling System Repair Status after the Initial Operation of HANARO Young-Chul Park(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Introduction of Measuring Instruments Used at Sodium Thermal Hydraulic Test Facilities in KAERI Tae-Joon Kim, Tae-Ho Lee, In-Koo Hwang, Ji-Young Jeong, Jong-Hyeun Choi, Jong-Man Kim, Byoung-Hae Ch PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Analysis of Local Recirculation Flow under Sub-channel Blockage Accident Won-Pyo Chang, Young-Min Kwon, Ki-Suk Ha, and Hae-Yong Jeong(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Effect of Molten Steel on CDA Energetics S.D.Suk and H.Y.Jeong(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Long-term Cooling Capability of KALIMER-600 PDRC Kwi-Seok Ha, Young-Min Kwon, Won-Pyo Chang, Kwi-Lim Lee, and Hae-Young Jeong(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) An Automatic Approach to the Stabilization Condition in a HIx Distillation Simulation Jiwoon Chang, Youngjoon Shin, Kiyoung Lee, Yongwan Kim, and Jonghwa Chang(KAERI) Cheung Youn(CNU) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) A Scoping Analysis of the Performance Test Loop of PDRC with the MARS-LMR Code Kwi Lim Lee, Kwi Suk Ha, and Hae-Yong Jeong(KAERI) PDF보기 -
Last Modified : 1998-Autumn