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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2007-Spring 제5분과 원자력안전 Effect of Mixing Vane on Critical Heat Flux in 2x3 Rod Bundle with R-134a Byung Soo Shin, Soon Heung Chang(KAIST) PDF보기 -
2007-Spring 제5분과 원자력안전 Development of RELAP/CANDU Thermal/Mechanical Model for Fuel Channel Analysis Kang-Moon Lee(ACT), Man-Woong Kim, Yong-Ho Ryu(KINS) PDF보기 -
2007-Spring 제5분과 원자력안전 Transient Performance Tests of a NSSS Thermal-Hydraulic Model for the APR1400 Simulator Jeong Kwan Suh, Jin Hyuk Hong, Myeong Soo Lee(KEPRI) PDF보기 -
2007-Spring 제5분과 원자력안전 The Measurements of Natural Convection Heat Transfer in Enclosures Using Analogy Experimental Methodology Bum-Jin CHUNG, Deok-Won MOON and Bong-Jin KO(CNU) PDF보기 -
2007-Spring 제5분과 원자력안전 Thermal-Hydraulic Analysis of a NTD System during Irradiation Jong-Hark Park, Hak-Sung Kim, Sang-Jun Park, Heonil Kim(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Influence of Asymmetric Gap Conductances in Annular Fuel on Thermal Hydraulics Kun-Ho Chun, Tae-Hyun Chun, Yong-Sik Yang, Chang-Hwan Shin, Keun-Woo Song(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Potential Concerns on the Realistic Evaluation of LBLOCA in APR-1400 Byung Gil Huh, Young Seok Bang, Deog-Yeon Oh, In-Goo Kim and Sweng Woong Woo(KINS) PDF보기 -
2007-Spring 제5분과 원자력안전 The Effect of PT Creep in Loss of Flow Accident for CANDU NPP Kim Yun Ho, Kim Yong Bae(KEPRI) PDF보기 -
2007-Spring 제5분과 원자력안전 Grid effects on the post-CHF heat transfer in one rod bundle geometry Kwi Lim Lee, Soon Heung Chang(KAIST) PDF보기 -
2007-Spring 제5분과 원자력안전 Improvement of Numerical Stability of the MATRA Code by Using a Uniform Pressure Drop with an Effective Loss Coefficient Kyong-Won Seo, Dae-Hyun Hwang, Chung-Chan Lee(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 APR1400 Locked Rotor Transient Analysis using KNAP Dong-Hyuk Lee, Yo-Han Kim, Sang Jun Ha(KEPRI) PDF보기 -
2007-Spring 제5분과 원자력안전 Three Dimensional CFD Analysis on Containment Pool Recirculation in ECCS Sump Performance Evaluation Jonguk Kim, Soon Joon Hong, Byung Chul Lee(FNC), Jong Woon Park(KHNP) PDF보기 -
2007-Spring 제5분과 원자력안전 A Qualification for GOTHIC Efficiency Input Model of Component Cooling Water System with FlowMaster II program Wan Jung Song(ENERGEO), Dong Soo Song, Choong Sup Byun, Hwang Yong Jun(KEPRI) PDF보기 -
2007-Spring 제5분과 원자력안전 Evaluation of thermal stratification in the S/G and development of preventing device Bum-Su Youn, Chul-Hong Kim, Kwang-Ho Lee, Sang-Nyung Kim(KHU) PDF보기 -
2007-Spring 제5분과 원자력안전 A Validation of the CATHENA Fuel Channel Model for a Post Blowdown Analysis against a High Temperature Thermal-Chemical Experiment for a Ballooned CANDU Fuel Channel Bo Wook Rhee, Joo Hwan Park(KAERI) PDF보기 -
Last Modified : 1998-Autumn