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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Analysis of Random Turbulent Flow Load in Steam Generator of APR1400 under Normal Operation Condition Sang-Gyu Lim, Sung-Chang You, and Han-Gon Kim(KHNP) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CCFL Model of the SPACE Code and Its Validation Myung Taek oh, Chan Eok Park, Jong Joo Sohn, and Eun Kee Kim(KEPCO E&C) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Validation of CUPID Code for a Subcooled Boiling Test Ik Kyu Park, Jungwoo Kim, Hyung Kyu Cho, and Han Young Yoon(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Steady-State Calculation of the ATLAS Test Facility Using the SPACE Code Hyoung Tae Kim, Ki Yong Choi, and Kyung Doo Kim(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) System Model Initialization for Nan-LOCA Analysis Using SPACE Code J. C. PARK, E. J. Lee, C. S. Lee, and E. K. Kim(KEPCO E&C) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of a Subchannel Code MATRA for OECD/NRC PSBT Benchmark Exercises Dae-Hyun Hwang, Seong-Jin Kim, and Kyong-Won Seo(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) MARS Code Simulation of A Cold Leg Intermediate Break LOCA at ROSA-2/LSTF Xin Guo Yu and KiYong Choi(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Numerical Investigation on Transient Behavior of Steam-gas Pressurizer in Integral PWR Yeon-Gun Lee, Jong-Won Kim, and Goon-Cherl Park(SNU) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Numerical Analysis on Temperature Distribution in the Reactor Internals of SMART Kyung Min Kim, Byoung In Lee, Dong hwi Lee, and Hyung Hee Cho(YONSEI Univ.,) Jin Seok Park and Young PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Introduction of Integral Test Facility, OSU-MASLWR and Steady State Calculation Young-Jong Chung, Sung Won Lim, and Won-Jae Lee(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) On PWR Fuel Failure Thresholds and Core Coolability Limits Seunghoon Ahn, Joosuk Lee, and Sungsik Kang(KINS) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of Thermal-hydraulic Behavior Following the Spray Event at Shinkori Unit 1 Using MARS Code Young Seok Bang, Byung Gil Huh, Seung Hoon Ahn, and Sweng-Woong Woo(KINS) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simulation of Total Loss of Electric Power Accident in the PWR Seung Wook Lee, Kyung Doo Kim, and Chang Sup Lee(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of Methodology for Evaluation of Chemical Effects on Sump Screen Performance Testing Young Wook CHUNG, Jae Seon CHO, Byung Il KWON, and Hee Kwon KU(FNC Tech.) Yu Jung CHOl and Hyeong Ta PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Best Estimate Prediction of NFR with Uncertainty Following a LBLOCA of CANDU Plants Santosh Kumar Pradhan(AERB) Young Seok Bang(KINS) PDF보기 -
Last Modified : 1998-Autumn