-->

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Seismic Soil-structure Interaction Analysis of a Consolidated Dry Storage Module for CANDU Spent Fuels Young Gon Kang, Jeong Hyoun Yoon, Chun-Hyung Cho, and Heung Young Lee (KHNP) Kyu-Sup Choi, In-Su Jeo PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Seismic Isolation Studies and Applications for Nuclear Facilities Young-Sun Choun (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Simulation of Tsunami Propagation at East Sea Along the Korean Peninsula Keum-Seok Kang and Weon-Hak Choi (KAERI) Chong-Hak Kim (KHNP) So-Beom Jin (KINS) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Study on the Grid Sensitivity of the CFD Analysis for the Thermal Mixing Test H. S. Kang, Y. S. Kim, H. G. Jun, Y. J. Youn, and C. H. Song (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 CFD Prediction of Thermal-hydraulic Characteristics Inside a Containment of a CANDU-6 Reactor Manwoong Kim, Yong Seog Choi, and Hyun Kook Kim (KINS) Hyun Suk Nho (ATES) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Overall Instrumentations for the ATLAS Integral Effect Test Program B. J. Yun, K. H. Kang, B. D. Kim, and W. P. Baek (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Air-water Multidimensional Flow Characteristics on Vertical Flat Wall Won J. Kim and Kune Y. Suh (SNU) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Scalability Analysis of Large Loss-of - coolantaccident at 8% Power Level for APR1400 and ATLAS Soon Joon Hong and Byung Chul Lee (FNC Tech) Heedo Lee (KOPEC) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Comparative Analysis of ATWS for OPR1000 by Using RETRAN-3D and CESEC-III Codes Sang IL Lee, Shin Whan Kim, and Eun Kee Kim (KOPEC) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Frequency Characteristics of Thermal Fluctuations Induced by Triple Jets Ho-Yun Nam, Min-Joon Kim, Jong-Man Kim, and Byoung-Hae Choi (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Assessment of Turbulence Models and Its Application to Pebble Bed Reactor J. J. Lee, S. K. Kang, S. J. Yoon, and G. C. Park (SNU) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 A Comparative Study Between a SGTR and a SG Module Pipe Break Accident of the Integral Type Reactor H. K. Kim, Y. J. Chung, G. H. Lee, H. C. Kim, and S. Q. Zee (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Heat Transfer Enhancement of Nanofluid in Natural Convection of an Enclosure Heated from Below In Cheol Bang, Eung Soo Kim, and Soon Heung Chang (KAIST) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 Design of Graph Analysis Model to Support Decision Making Sang-Ha An, Sung-Jin Lee, and Soon-Heung Chang (KAIST) Sung Ho Kim and Tae Woon Kim (KAERI) PDF보기 -
2005-Autumn 제5분과 : 원자력안전 - 중대사고 CHF Characteristics of R-134a Flowing Upward in an Annulus Geometry Kwi Lim Lee and Soon Heung Chang (KAIST) PDF보기 -
Last Modified : 1998-Autumn