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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) The Evaluation of IFPE Database by FRAPCON-3 Code -IFA-432, AECL Bundle NR Yeonseung Kim, Hyounju Yoon, Jungsoo Kim, Hyonggun Shim, and Kwangheon Park(KHU) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) On-line Inverse Count Rate Ratio Measurement System during Core Reload Ho-Cheol Shin and Dong-Hwan Park(KEPRI) Sae-Hyun Oh and Seok-Jean Ryu(USERS) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) Test on Similarity between the Flooded and Optimum Moderation Conditions of the Spent Fuel Storage Pool Gil Soo Lee, Chang Sun Jang, and Sweng Woong Woo(KINS) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) Sensitivity Study on Input Parameters Used in the Spent Fuel Pool Cooling Capacity Evaluation Hyung Seok Kim, Dong Keon Kim, and Won Tae Kim(ENESYS Co.,) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) A Comparison of Two Spatial Difference Schemes with an Unstructured Triangular Mesh for a Twodimensional Geometry Jong Woon Kim, Ser Gi Hong, and Young-Ouk Lee(KAERI) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) A Preliminary Study on Calculation of Inter-pebble Dancoff Factor in a Pebble Type Core Songhyun Kim, Hong Chul Kim, and Jong Kyung Kim(HYU) Soon Young Kim(ITRS), Jae Man Noh(KAERI) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) Feasibility Study on TRU Deep-burn with Inert Matrix Fuel in an MHR Chang Keun Jo, Yonghee Kim, and Jae Man Noh(KAERI) F. Venneri(LT) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) Decay Heat Analysis of a PMR200 VHTR Core by Using McCARD and ORIGEN2 Codes Hyun Chul Lee, Wei Li, Chang Keun Jo, and Jae Man Noh(KAERI) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) Dynamic Analysis of Fast Reactor Scenario by Using DANESS Code Chang Joon Jeong and Won. Il. Ko(KAERI) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) Benchmark Analysis of KALIMER-600 Simplified Core Model by Using ECCO/ERANOS2.1 System Jae Woon Yoo, Jin Wook Jang, and Yeong Il Kim(KAERI) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) An SP3 Nodal Method Applied to Fast Reactor Core Analysis Yeong-il Kim, Jaewoon Yoo, and Dohee Hahn(KAERI) Chang Hyo Kim(SNU) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) Preliminary Development of the MARS/FREK Spatial Kinetics Coupled System Code for Square Fueled Fast Reactor Applications Moo Hoon Bae and Han Gyu Joo(SNU) PDF보기 -
2009-Spring 제 2 분과 원자로물리 및 계산과학(Reactor Physics and Computational Science) Analysis of Metallic Uranium Fueled BFS Experiments Using McCARD Ho Jin Park, Min Su Kwak, Han Gyu Joo, and Chang Hyo Kim(SNU) Jaewoon Yoo(KAERI) PDF보기 -
2009-Spring 제 3 분과 방사성폐기물관리(Radioactive Waste Management) Infrared Spectroscopy of Uranium Oxides by ATR Technology Jong-Goo Kim, Yang-Soon Park, Hyun-Kyum Kim, Yeong-Keong Ha, and Kyuseok Song(KAERI) PDF보기 -
2009-Spring 제 3 분과 방사성폐기물관리(Radioactive Waste Management) Application of a Capillary Electrophoresis to the Speciation of Eu(III) Complexes in an Aqueous Solution K. K. Park, H. -R. Cho, and E. C. Jung(KAERI) PDF보기 -
Last Modified : 1998-Autumn