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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) Feasibility Analysis on Simulation of PLCS Malfunction Event Using SPACE Code Ung Soo Kim, Cheol Shin Lee, and Jong Joo Sohn(KEPCO E&C) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Applicability Evaluation on the Conservative Metal-water Reaction(MWR) Model mplemented into the SPACE Code Suk-Ho Lee, Sung-Chang You, and Han-Gon Kim(KHNP) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) ATWS Analysis for Replacement of Steam Generator Using MARS-KS Won Joon Chang, Seung Hoon Ahn, Deog yeon Oh, and Kwang Won Seul(KINS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) MARS Code Reflood Model lmprovements and Comparisons with Flecht-seaset and RBHT Tests Moonkyu Hwang and Bub-Dong Chung(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Influence on Accuracy of Flow Rate under Position of Orifice Flowmeter Using Numerical Analysis Nam-Seok Kim, Sang-Kyu Lee, Byung-Soo Shin, Chan-Ki Moon, and O-Hyun Keum(KINS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Performance Assessment of Passive Heat Exchanger with Horizontal Tube Using RELAP5 Kyung Jin Lee, Soon Joon Hong, and Byung Chul Lee(FNC Tech) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Numerical Analysis for IFM Grid Effect on 5x5 Rods Bundle Seong Jin Kim, Jeong Hun Cha, Kyong Won Seo, Tae Woo Kim, Hyuk Kwon, and Dae Hyun Hwang(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Application of the CUPID Code for the Simulation of Multi-dimensional Thermal Hydraulic Phenomena in Advanced Power Reactors Hyoung Kyu Cho, Seung-Jun Lee, and Han Young Yoon(KAERI) Jae Jun Jeong(PNU) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Coherent Calculation for Air-water Flow and Boiling Flow by Using CUPID Code Ik Kyu Park, Han Young Yoon, and Hyung Kyu Cho(KAERI) An Sook, Seol(KAIST) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Best Estimate Approach for the Simulation of Void Reactivity of CANDU Type Reactor Using the MARS Code Kap Kim(KINS) Byoung Sub Han(ENESYS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) ATLAS Steam Generator Tube Rupture Accident Simulation Using SPACE Code Chang-Keun Yang, Sang-Jun Ha, and Hwang-Yong Jun(KHNP) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Optimization of Heat Transfer Mode Determination in TASS/SMR-S Core Heat Transfer Model Soo Hyoung Kim, Seong Wook Lee, and Young-Jong Chung(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Performance Evaluation for the Diameter and Material of Condensation Heat Exchanger Using the TASS/SMR-S Code In Sub Jun, Soo Hyoung Yang, Kyoo Hwan Bae, and Young Jong Chung(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Computation of Pressure Drop in Cross-flow through an In-line Tube Bundle Youngmin Bae, Yu Mi Jeon, Yeong-Gil Kim, Seung Heon Yang, Han-Ok Kang, Young-In Kim, Cheon-Tae Park, PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Effect of Core Residual Heat on Success Criteria during the Shutdown and Low Power Operation Moon-Oh Kim and Hee-Do Lee(ACT Co., Ltd.) Goon-Cherl Park(SNU) PDF보기 -
Last Modified : 1998-Autumn