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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Comparison of High Temperature Elastic Modulus of Selected Nuclear Graphites Eung-Seon Kim and Sung-Deok Hong(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Development of Process Heat Exchanger (PHE) for Nuclear Hydrogen Production System Jae-Won Park, Hyung-Jin Kim, Sunmog Yeo, and Sung-Deok Hong(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Gamma Energy Production Analysis in KALIMER-600 Core Min-Ho Baek, Won S. Park, Sang-Ji Kim, and Jaewoon Yoo(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) The Preliminary Test of the Annular Linear Induction EM Pump Hee Reyoung Kim, Byung Hae Choi, Jong-Hyeun Choi, and Yong Bum Lee(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Development of a Large Cold Trap Design Technology-I Jong-Hyeun Choi, Jong-Man Kim, Ji-Young Jeong, Tae-Joon Kim, and Yong-Bum Lee(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Water Mock-up for the Sodium Waste Treatment Process Ho-Yun Nam, Jong-Man Kim, Byung-Ho Kim, and Yong-Bum Lee(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Investigation of Sodium-CO2 Interaction in Advanced SFR Power Conversion System Jae Hyuk EOH, Yong-Bum LEE, and Seong-O KIM(KAERI) Hee Cheon NO(KAIST) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Multi-target Wastage Phenomena on Steam Generator Tubes during an SWR Event Ji-Young Jeong, Jong-Man Kim, Tae-Joon Kim, Jae-Hyuk Eoh, Jong-Hyeun Choi, and Yong-Bum Lee(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Testing of Electromagnetic Flow Rate Transducer Used at Sodium Thermal Hydraulic Test Facilities in KAERI Tae-Joon Kim, Jae-Hyuk Eoh, In-Koo Hwang, Ji-Young Jeong, Jong-Man Kim, Byoung-Hae Choi, Yong-Bum Le PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Design Study on the Rotating Plug Size of an Advanced SFR Demonstration Plant S. H. Kim and J. B. Kim(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Comparison Study on Finite Element Model for Modal Analysis of the SFR High Temperature Piping Chang-Gyu PARK and Jong-Bum KIM(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) FEM Simulations of Leaky Lamb Wave in Ultrasonic Waveguide Sensor Jin-Ho Bae, Young-Sang Joo, and Jong-Bum Kim(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) High Temperature Fatigue Crack Growth Tests for Mod.9Cr-1Mo Steel at 0.1 Hz Loading Frequency Jong-Bum Kim, Chang-Gyu Park, and Hyeong-Yeon Lee(KAERI) Jong-Hoon Lee and Bum-Joon Kim(SKKU) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Core Design of a 600 MWe Uranium Fueled TRU Burner Reactor Hoon Song, Won Seok Park, and Sang Ji Kim(KAERI) PDF보기 -
2011-Spring 제1분과 : 원자로시스템기술(Reactor System Technology) Radial Core Expansion Reactivity Model in Limited Free-Bowing Reactor Constraint System Young-Min KWON, Kwi-Lim LEE, Kwi-Seok HA, Hae-Yong JEONG, and Won-Pyo CHANG(KAERI) PDF보기 -
Last Modified : 1998-Autumn