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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Study on Equipment Qualification Technology of MOV Actuator for Continued Operation Byung-ju Lim, Chang-dae Park, and Chi-sung Song (KIMM) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Nonlinear Dynamic Analysis of Reinforced Concrete Planar Structures Do-Yeon Kim and In-Kil Choi (KAERI) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Example Performance-Based Site-Specific Design Earthquake for Nuclear Power Plant SSCs In-Kil Choi (KAERI) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Experimental Study on Temperature Behavior of SC Structures K. J. Lee, K. W. Ham, D. S. Park, and K. J. Kwon (KEPRI) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Conceptual Layout of an AHR Building and Facilities Jeong-Soo Ryu, Hee-Taek Chae, and Cheol Park (KAER) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Nonlinear FE Analysis for PCCV 1/4 Model Using NUCAS Code Hong-Pyo Lee and Young-Chul Song (KEPRI) Young-Sun Choun (KAERI) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Experimental Study on Bending and Shear Behavior of SC Structures Under Out of Plane Load D. S. Park, K. J. Lee, K. W. Ham, and Y. P. Suh (KEPRI) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Mitigation of Over-conservatism in Fatigue Analysis of the Pressurizer Surge Line Chan Kook Moon, Jang Gon Lee, and Tae Soon Kim (KHNP) Sung Bong Han (GNEC) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Safety Analysis of an Annular Fuel in a LBLOCA Using the MARS Code Hyoung Tae Kim, Kyoo Hwan Bae, and Tae Hyun Chun (KAERI) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) MARS3.1 Assessment Using Ulchin 5 Pre-operational Test,”Turbine Trip and Natural Circulation” Yong Jin Cho, Seung-Hoon Ahn, Sang Kyu Lee, Chang Wook Huh, and Jong Kap Kim (KINS) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Sensitivity Analysis on Critical Flow Model of RETRAN-3D Code on OPR1000 ATWS Event Yeon Kyoung Bae and Hyeong Taek Kim (KHNP) Sung Jae Cho (UDU) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Application of RELAP5/MOD3.3 to Calculate Thermal Hydraulic Behavior of the Pressurizer Safety Valve Performance Test Facility Chang Hyun KIM, Young Ae KIM, Seung Jong OH, and Jong Woon PARK (KHNP) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Application of KIMERA Methodology to Kori 3&4 LBLOCA M/E Release Analysis Jeung Hyo Song, Byung Heon Hwang, and Cheol Woo Kim (KOPEC) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) The Analysis of Loop Seal Purge Time for the KHNP Pressurizer Safety Valve Test Facility Using the GOTHIC Code Young Ae KIM, Chang Hyun KIM, Gab Joo KWEON, and Jong Woon PARK (KHNP) PDF보기 -
2007-Autumn 제5분과 : 원자력안전 (Division of Nuclear Safety) Development of Safety Margin Analysis Methodology on Aging Effect for CANDU Reactors (II) Manwoong Kim, Sang Kyu Lee, Hyun Koon Kim, Kun Joong Yoo, and Yong-Ho Ryu (KINS) Yong Won Choi and U PDF보기 -
Last Modified : 1998-Autumn