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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) Experimental Study on Flow Regime Transition in an Inclined Pipe Min Seok Ko, Bo An Lee, Sung Yong Lee, Yeong Jun Jang, Yoon Jeong Hong, and Sin Kim(JNU) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) TR-PIV Performance Test for a Flow Field Measurement in a Single Rod Test Section Ju Yong Park, Chang Hwan Shin, Chi Young Lee, Dong Seok Oh, and Wang Kee ln(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Detection of Microlayer Geometry in Nucleate Boiling Using nterferometry of nfrared Light Junkyu Song and Hyungdae Kim(KHU) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Translating Chord Length Distribution into Bubble Size Distribution Using Numerical and Analytical Backward Transforms Hoang Nham Hien(UST) B. J. Yun and C. H. Song(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Experimental Study on Pure Steam Condensation in a Vertical Tube Ki Hoon Yang, Dong Eok Kim, Kyung Won Hwang, Young Ho Ha, and Moo Hwan Kim (POSTECH) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Effects of Al2O3 and Carbon Nanofluids on Reflood Heat Transfer in a Long Vertical Tube Seung Won Lee and In Cheol Bang(UNIST) Se-Young Chun and Chul Hwa Song(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Influence of the Chimney Dimensions on the Heat Transfer of a Vertical Cylinder in a Duct Chul-Kyu Lim and Bum-Jin Chung(JNU) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Natural Convection Mass Transfer inside Vertical Cavities with Active/Inactive Lids Gyeong-Uk Kang and Bum-Jin Chung(JNU) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Natural Convection Heat Transfer of Two Vertically Staggered Cylinders Myeong-Seon Chae and Bum-Jin Chung(JNU) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis of a Loss of Condenser Vacuum Event Using the SPACE Code Eun Ju Lee, Cheol Shin Lee, and Jong Joo Sohn(KEPCO E&C) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Droplet Prediction for Annular Flow in SPACE Code Byoung Jae Kim, Eo Hwak Lee, and Kyung Doo Kim(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of ATLAS 100% DVI Line Break Using TRACE Code Byung Gil Huh, Young Seok Bang, Ae-ju Cheong, and Sweng Woong Woo(KINS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of Helical Coil Heat Transfer Models of MARS-KS Code by Using Experimental Data from MASLWR Test Facility Ju Yeop Park(KINS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simulation of 50% DVI Line SBLOCA in the ATLAS Integral Test Facility Using MARS-3D Code Hyoung Tae Kim and Ki Yong Choi(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) MARS-KS Assessment Results on B9802 Test in RD-14M Facility Joosung KIM, Kap KIM, and Kwangwon SEUL(KINS) PDF보기 -
Last Modified : 1998-Autumn