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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) CFD Analyses of Hydrogen Flame Acceleration in the ENACCEF and IRWST Facilities Hyung Seok Kang, Kwang-Soon Ha, and Sang-Baik Kim(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Effects of Nanofluid for In-Vessel Retention External Reactor Vessel Cooling on Critical Heat Flux Using Pool Boiling Experiments Sung Dae Park, Sarah Kang, Seung Won Lee, and In Cheol Bang(UNIST) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Introduction of VESTA Facility and Melting Test Results Hwan Yeol Kim, Jong Hwan Kim, Beong Tae Min, Seong Wan Hong, Rae Joon Park, and Jin Ho Song(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Corium Spreading in the Reactor Cavity during Severe Accident in the SMART Youngho Jin(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Study on the On-Line Maintenance Risk Assessment Methods Jae-Ho Kim and Moosung Jae(HYU) Sang-Kyu Ahn and Chang-Ju Lee(KINS) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Reliability Assessment Method for the VHTR Safety Systems Hyung-sok Lee and Moosung Jae(HYU) Yong-wan Kim(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Calculation of Core Damage Frequency for the Change of the Common Cause Failure Parameters According to the Testing Strategies Dae Il Kang, Kilyoo Kim, Young Ho Jin, and Tae-Woon Kim(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Modeling of Cabinet Fire in Switchgear Room Using Fire Dynamic Simulator Dae Il Kang, Jong Seuk Park, and Ho Gon Lim(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Local Velocity Measurement in DYNAS Having 2D Slab Test Section Using Impedance Measurement Technique S. Kim, D. J. Euh, B. D. Kim, W. M. Park, B. J. Yun, C. -H. Song, and K. D. Kim(KAERI) J. H. Bae and PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Bubble Size Effect on the Interfacial Area Transport in Gas Liquid Two-phase Flow V. T. Nguyen, C-. H. Song, and D. J.Euh(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Droplet Measurement Across a Grid Spacer in a 2x2 Rods During Reflood Byoung Jae Kim, Hyoung Kyu Cho, Jong Kuk Park, and Sang Ki Moon(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Ultrasonic Measurement of Water Layer Thickness by Flow Pattern Profile in a Horizontal Air Water Loop Kil-Mo Koo, Chul-Hwa Song, and Young-Rho Cho(KAERI) Seung-Tae Lee(UST) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Flow Boiling CHF Experiments Using Nanofluid under Different Heating Rate Tae Il Kim, Young Taek Jee, and Soon Heung Chang(KAIST) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Experimental Study on the CHF Enhancement of the Nanofluids Containing Exfoliated Graphite Nanoplatelets(xGnP) Eun ju Park, Hyung wook Park, Sung dae Park, and In cheol Bang(UNIST) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Experiment on Upward Supercritical Carbon Dioxide Flow in a Vertical Tube with Metallic Surrounding Hyung M. Son, Jae S. Yoo, and Kune Y. Suh(SNU) PDF보기 -
Last Modified : 1998-Autumn