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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) Passive Safety Characteristics of the 1200MWe GEN-IV Sodium-Cooled Fast Reactor Young-Min KWON, Kwi-Lim LEE, Kwi-Seok HA, Hae-Yong JEONG, and Won-Pyo CHANG(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Development of a Water Scaled Model for the Thermal Hydraulic Study of 600MWeSFR J.E.Cha, S.H.Lee, S.O.Kim, and Y.I.Kim(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Power Control Logic Evaluation of RRS for SMART Yu-Lim Jeon, Han-Ok Kang, Seong-Wook Lee, and Cheon-Tae Park(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Core Thermal-Hydraulic Conceptual Design for the Advanced SFR Design Concepts Chungho Cho, Jinwook Chang, Jae-Woon Yoo, Hoon Song, Sun-Rock Choi, Won-Seok Park, and Sang-Ji Kim(K PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Investigation of a Wastage Effect by a Potential CO Ingress in a Supercritical CO Power Conversion System of an SFR Jae Hyuk EOH, Ji-Young JEONG, Jong-Man KIM, and Seong-O KIM(KAERI) Hee Cheon NO(KAIST) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Analytical Study for Development of Cold Trap Design Technology Jong-Hyeun Choi, Byoung-Hae Choi, Jong-Man Kim, Ji-Young Jeong, Byung-Ho Kim, and Yong-Bum Lee(KAERI PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Improvements of Physical Models in TRITGO Code for Tritium Behavior Analysis in VHTR Jun Soo Yoo, Nam-il Tak, and Hong Sik Lim(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Design of System Heat Balance in 600 MWe Sodium-cooled Fast Reactor Ji-Woong Han, Jae-Hyuk Eoh, Eui-Kwang Kim, and Seong-O Kim(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Preconceptual Component Arrangement for a Pool-type Sodium-cooled Fast Reactor of 1200MWe Capacity Chang-Gyu PARK, Jae-Han LEE, and Jong-Bum KIM(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Decay Heat Impact on the Maximum Transient Fuel Temperature of the Various TRU Compositions in a Deep-Burn MHR Core Ji Su Jun, Hong Sik Lim, and Chang Keun Jo(KAERI) Francesco Venneri(LT U.S.A) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Computational Assessment of Bypass Flow in a Multi-Block Air Test Min-Hwan Kim, Hong-Sik Lim, and Nam-il Tak(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Wastage Behavior of Modified 9Cr-1Mo Steel Tube Material by Sodium-Water Reaction (II) Ji-Young Jeong, Jong-Mam Kim, Tae-Joon Kim, Jong-Hyeun Choi, Byung-Ho Kim, and Yong-bum Lee(KAERI) N PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Proactive Role of Regulation for SMART Design Certification Namduk Suh and Changwook HUH(KINS) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Structural Evaluations of the Reactor Vessel Head at Elevated Temperature S.H.Kim, G.H.Koo, and J.B.Kim(KAERI) PDF보기 -
2010-Spring 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) Design of a Visualization System of Flow Boiling in a Vertical Tube with a Sulfuric Acid DongUn Seo and G.C.Park(SNU) C.S.Kim, S.D.Hong, and Y.W.Kim(KAERI) PDF보기 -
Last Modified : 1998-Autumn