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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Computational Analysis of Controlled Power Source for Transient Fusion Reactor Power Conversion B. Halimi and Kune Y. Suh(SNU) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Phenomena and Detection of Gas Accumulation in Piping Systems D. Y. Lee, S. S. Jeon, and S. J. Hong(FNC Tech.) Y. J. Song(Westinghouse Electronic Co.,) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Measurement of Pipe Slope with Laser Scanning Technique D. Y. Lee, S. S. Jeon, and S. J.Hong(FNC Tech.) S. C. Park(ENGUARD) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) OPR1OOO Steady State Analysis Using the SPACE Code Bum Soo, Youn, Dong-Hyuk, Lee, and Se-Yun, Kim(KHNP) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) MARS-KS Code Assessment for UCB-Kuhn Condensation Test Jin-Hyuck Kim, Ju Yeop Park, and Joo-Sung Kim(KINS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Analysis on the Lower Core Support Plate at the Core Inlet of SMART Test Facility Y. M. JEON, Y. G. KIM, Y. M. BAE, Y. I. KIM, C. T. PARK, and S. CHOI(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of Pressurizer Transients Using the SPACE Code Dong-Hyuk Lee, Bum-Soo Youn, and Se-Yun Kim(KHNP) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Non-LOCA Safety Analysis for the APR1OOO Preliminary Design Yo-Han Kim, Chang Keun Yang, and Jae Hwa Koh(KHNP) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Benchmark Simulation of Turbulent Flow through a Tube Bundle G. H. Lee and S. W. Woo(KINS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Off-take Model of the SPACE Code and Its Validation Myung Taek Oh, Chan Eok Park, and Jong Joo Sohn(KEPCO E&C) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Analysis of Condensation and Two-phase Flow in PCHX of PAFS Kwang Chu Kim, Ho Je Seong, and Hee Jin Ko(KEPCO E&C) Choengryul Choi(ELSOLTEC) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Radionuclide Release after LBLOCA with Loss of Class IV Power Accident in CANDU-6 Plant Hoon Choi(KHNP) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Safety Assessment of Void Increase in Reactor Coolant System Induced by LOP/SLB Kun Ho Chun, Tae Young Choi, Young Koo Kim, and Choon Ho Park(KEPCO NF) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of Condensation Models in SPACE in the Presence of Noncondensable Gas Ji-Hun Kim, Jin-Hwa Yang, and Goon-Cherl Park(SNU) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of MARS-KS Codes on LBLOCA for CANDU Type Reactor Jin-Hyuck Kim, Joo-Sung Kim, and Kwang-Won Seul(KINS) PDF보기 -
Last Modified : 1998-Autumn