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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) Experimental Study of Subcooled Flow Boiling CHF Enhancement on Modified Zirconium Alloy Tube With Micro Structure Soon Ho Kang, Ho Seon Ahn, Hang Jin Jo, Seol Ha Kim, Gunyeop Park, Ji Min Kim, and Moo Hwan Kim(POST PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Hydraulic Test for SMART Reactor Flow Distribution: Run No. SCOP-E-01 D. J. Euh, Y. J. Youn, I. C. Chu, Y. J. Ko, T. S. Kwon, and S. J. Lee(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Separate Effects of Surface Roughness, Wettability and Nano-porosity on the Leidenfrost Point Temperature of Water Hyungdae Kim(KHU) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of Mixed Convection Heat Transfer Correlations at Supercritical Pressures Yoon-Yeong Bae, Sung-Deok Hong, and Yong-Wan Kim(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A SBLOCA Test of Safety Injection System for SMART with the VISTA-ITL and Its Simulation with the MARS-KS Code Hyun-Sik Park, Byoung-Yeon Min, Rae-Joon Park, Sang-Ki Moon, Hwang Bae, and Sung-Jae Yi(KAERI) Doo-H PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Review of the Characteristics of Steam Plume Jet in Water Yeon-Sik Kim, Ki-Yong Choi, and Chul-Hwa Song(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Large-scale Flow Pulsation in Tight Square Arrayed Rod Bundles of Nuclear Reactor Taehwan Kim, Kyung Min Kim, and Hyung Hee Cho(YONSEI Univ.,) Chang Hwan Shin and Wang-Kee ln(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Pressure Variation Analysis in the Down-scaled SMART Model Dong hwi Lee, Kyung Min Kim, Byoung In Lee, and Hyung Hee Cho(YONSEI Univ.,) Jin Seok Park and Kyeon PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Study on Thermal-hydraulic Phenomena Identification of Passive Heat Removal Facilities J. Y. Park(KINS) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of Capability of MARS Code for Safety Evaluation of APR+ PAFS Seong Su Jeon and Byung Chul Lee(FNC Tech.) Ju Yeop Park and Kwang Won Seul(KINS) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) APR+ PAFS Cooling Performance Analysis Using RELAP5 Kyung Jin Lee and Soon Joon Hong(FNC Tech.) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of Heat Removal Capability of Passive Auxiliary Feedwater System Using MARS Code Yun-Je Cho, Byong-Uhn Bae, Byong-Jo Yun, and Chul-Hwa Song(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Performance Analysis of APR+ PAFS for CDF Evaluation Sang Hee Kang and Han Gon Kim(KHNP) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) MARS-KS Calculations for ATLAS 6-inch Cold Leg Break Test (DSP-02) Dong-Gu Kang, Joo-Sung Kim, Seung-Hoon Ahn, and Kwang-Won Seul(KINS) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Effects of Fuel Burnup and Rod Performance on the PCT during LBLOCA Joosuk Lee, Byung-Gil Huh, Young Seok Bang, Haedong Jeong, Andong Shin, and Swengwoong Woo(KINS) PDF보기 -
Last Modified : 1998-Autumn