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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2007-Spring 제5분과 원자력안전 Study on the Production of the Thermal Fatigue Crack for in-service inspection qualification mock-ups Dae-Hwan An, Gyu-Beom Lee, Jae-Seong Kim, Sang-Yul Lee, Bo-Young Lee(KAU) PDF보기 -
2007-Spring 제5분과 원자력안전 Performance Evaluation Technology for Air Operated Valves in NPPs Byoung Eui Lee, Sun Dong Shin, Woo Bang Lee(KHNP) PDF보기 -
2007-Spring 제5분과 원자력안전 Progressive Instability Behavior of Modified 9Cr-1Mo Steel Subjected to High Temperature Cycles Gyeong-Hoi Koo and Jae-Han Lee(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Thermal Fatigue Analysis of CANDU Feeder Pipe System Myung Jo Jhung, Dong Gu Kang, Jong Chull Jo(KINS) PDF보기 -
2007-Spring 제5분과 원자력안전 Residual Stress Assessment of Dissimilar Metals Welding for Pipelines at NPPs Using Support Vector Regression Man Gyun Na, Jin Weon Kim, and Dong Hyuk Lim(CNU) PDF보기 -
2007-Spring 제5분과 원자력안전 Design of Nuclear Power Plant Online Monitoring System Sang-ha An(KAIST), Song-kyu Lee(KOPEC), Yong-hoon Jeong, Soon-heung Chang(KAIST) PDF보기 -
2007-Spring 제5분과 원자력안전 A Review of The Deposit Influenced BOW Signals in The SG Tubes K. M. Min, K. Jeon, J. A. Park, T. E. Chung(KAITEC) PDF보기 -
2007-Spring 제5분과 원자력안전 Interface Capturing method for a Two-phase flow using the Lattice Boltzmann method Seungyeob Ryu, Cheon Tae Park, Jaekwang Seo, Juhyeon Yun, Sung-Quun Zee(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 The Flooding Water Source Analysis following the Feed Line Break at the Compartment outside Containment for Nuclear Power Plant Dong-Soo, Song(KEPRI), Young-Chan, Park(ACT) PDF보기 -
2007-Spring 제5분과 원자력안전 An application of the modified turbulent model for analyzing supercritical heat transfer phenomena in a nuclear system Kyoungwoo Seo, Cheon-Tae Park, Jae-Kwang Seo(KAERI), Moo-Hwan Kim(POSTECH), Michael L. Corradini(Uni PDF보기 -
2007-Spring 제5분과 원자력안전 MARS Simulation of the Steady-State and Transient Void Behaviors in an 8x8 Rod Bundle J. J. Jeong, D. H. Hwang and B. D. Chung(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Improvement of the Post-CHF Heat Transfer Model in the MARS Code Sang-Ki Moon, Se-Young Chun, Ki-Yong Choi, Seok Cho, Jong-Kuk Park, Won-Pil Baek(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 The analysis of temperature distribution for surveillance Capsule in reactor vessel of YGN unit 1 Chang-Keun Yang, Yo-Han Kim, Sang-Jun Ha(KEPRI) PDF보기 -
2007-Spring 제5분과 원자력안전 Simulation of a Flow Excursion in a Narrow Flow Channel by using the MARS Code C. Park, H.T. Chae, H. Kim(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Effects of the Location of Side Inflow Holes on Pool Boiling Heat Transfer in a Vertical Annulus Myeong-Gie Kang(ANU) PDF보기 -
Last Modified : 1998-Autumn