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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Development of a Safety Analysis Code for a Supercritical Water Cooled Reactor (SCWR) Han Young Yoon, Soo Hyung Kim, Hee Cheol Kim, and Yoon Yeong Bae (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 An Experimental Study on the Factors for the Performance of a Shutoff Unit in the Half-core Test Loop of HANARO Kyoung-Rean Kim and Yeong Garp Cho (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Instability in Liquid Zone Control System of CANDU Reactor Joon-Suk Ji (KAERI) Sang-Nyung Kim (KHU) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Refrigerator Control Methods and Heat Exchanger Operating Condition for the CNS Jungwoon Choi, Bong Soo Kim, Young-ki Kim, Kyehong Lee, and Hark Rho Kim (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Two Dimensional CFD Analyses on the Heat Transfer for a Supercritical Pressure CO2 Bong Hyun Cho, Young In Kim, and Yoon Yeong Bae (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Flow Behavior Analysis of the Inlet Plenum with Narrow Type Flow-skirt Using CFD Code Jong-hark Park, Hee-taek Chae, Cheol Park, Heon-il Kim, and Jun-hong Kim (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Development of a Detailed Sub-channel Model for the Safety Analysis of Liquid Sodium-cooled Reactor S. Heo, H. Y.Jeong, Y. M. Kwon, and D. H. Hahn (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Review of Thermal-chemical Experiments for a CANDU Fuel Channel Hyoung Tae Kim, Bo Wook Rhee, and Joo Hwan Park (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 A CFD Analysis of the Coolant Flow Characteristics in the HANARO Gee Y. Han, Heonil Kim, and Byung J. Jun (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 CFD Simulations on Flow Fields of the 16x16 ACE7TM Rod Bundle Spacer Grid SeungGeun Yang, HyunMi Hong, KangHoon Kim, HongJu Kim, Eung Jun Park, SunTack Hwang, and Young Koo K PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Predicting Velocity Profiles on the Inlet Nozzles for the Simulation of the Wolsong 2/3/4 Moderator Circulation Churl Yoon and Joo Hwan Park (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Sensitivity Study of Peak Cladding Temperature on the Operation Parameters for the 3-Pin Fuel Test Loop S. K. Park, D. Y. Chi, B. S. Shim, K. N. Park, S. H. Ahn, J. M. Lee, and C. Y. Lee (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Parameter Study of the Passive Residual Heat Removal System Flow Instability Han-Ok Kang, Taeho Lee, and Juhyeon Yoon (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Analysis of Impact of Power Uprate on Loss of RHR Events During Mid-loop Operation for Kori 3&4 Kee Soo Han, Han Rim Choi, and Eun Kee Kim (KOPEC) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Development of OPR1000 RCP Coast Down Flow Calculation Methodology with RETRAN Dong Hyuk Lee, Hye Jeong Yoon, Yo Han Kim, and Chang Kyung Sung (KEPRI) PDF보기 -
Last Modified : 1998-Autumn