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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Quality Assurance for Thermal Hydraulic Analysis Code, TASS/SMR-S Hee-Kyung Kim, Soo Hyoung Kim, and Young-Jong Chung(KAERI) Hyeon-Soo Kim(CNU) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Comparison of SKN 3&4 NCC Simulations Using SPACE and a Current Design Code Byung Heon Hwang, Il Soon Park, Myung Taek Oh, Chan Eok Park, and Jong Joo Sohn(KEPCO E&C) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) SPACE Code ECCX Component Model and Comparisons with RELAP5/Mod 3.3 Code Predictions Moonkyu Hwang, Sung-Won Bae, and Kyung-Doo Kim(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Numerical Study of Condensation Heat Exchanger Design in a Subcooled Pool: Correlation Investigation Hee Joon Lee and Yunjae Ju(KMU) Han-Ok Kang, Tae-Ho Lee, and Cheon-Tae Park(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Benchmark Simulation for the Development of the Regulatory Audit Subchannel Analysis Code G.H. Lee, C. Song, and S.W. Woo(KINS) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Effects of Curvature on the Turbulent Flow in a Helical Tube Dong-Hyeog Yoon and Kwang-Won Seul(KINS) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Conversion of Chord Length Data into Bubble Size Distribution: Generation of Chord Length Data and the Methodology Comparison Hoang Nhan Hien, D.J .Euh, and C-H. Song(KAERI) B.J .Yun(PNU) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Design Modification of Boron Injection Tank for a Westinghouse Type NPP Dong Soo Song(KHNP CRI) Song Kee Sung and Jae Il Lee(KEPCO NF) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of an Automatic Verification Program for Thermal-hydraulic System Codes J. Y. Lee, K. T. Ahn, S. H. Ko, Y. S. Kim, D. W. Kim, and J. J. Jeong(PNU) J. S. suh and Y. S. Cho(S PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of SPACE Code Using the LSTF 10% MSLB Test Yo-Han Kim, Chang Keun Yang, and Sang Jun Ha(KHNP CRI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of Natural Circulation Cooldown for the SMART Sook Kwan Kim, Koo Sam Kim, and Suk Ku Sim(en2t) Ju Yeop Park and Kwang Won Seol(KINS) Kyu Hwan Bae( PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Characteristics of Single Stage and Multi Stage Core DNBR Analysis Models Younhwa Lee and Joon Hyong Cho(KEPCO NF) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Magnetite Transport Characteristics in a CANDU Reactor Jun Ho Bae, Bo Wook Lee, and Jong Yeob Jeong(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Fluid to Fluid Modeling of R134a CHF in SMART 5x5 Rod Bundles Seong Jin Kim, Jeong Hun Cha, Kyong Won Seo, Hyuk Kwon, and Dae Hyun Hwang(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Sensitivity Study of Regional TDC in MATRA-S Code Using PSBT Benchmark Exercise Seong Jin Kim, Jeong Hun Cha, Kyong Won Seo, Hyuk Kwon, and Dae Hyun Hwang(KAERI) PDF보기 -
Last Modified : 1998-Autumn