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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2007-Spring 제5분과 원자력안전 Assessment of the RELAP5/MOD3.3 Critical Flow Model using the Experimental Data with Non-condensable gas Tae-beom Lee, Jae-hoon Lee, Chang-hwan Ban(KNFC) PDF보기 -
2007-Spring 제5분과 원자력안전 CHF Characteristics near the Critical Pressure in a 5x5 Heater Rod Bundle Cooled by R-134a Fluid: Effects of Spacer Grid and Unheated Rods S.Y. Chun, C.W. Shin and S.D. Hong(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Wettability of Heated Surfaces under Pool Boiling using Surfactant Solutions and Nano-fluids Won Joon Chang, Yong Hoon Jeong, Soon Heung Chang(KAIST) PDF보기 -
2007-Spring 제5분과 원자력안전 Local Flow Structure and Experimental Investigation of Interfacial Area Transport of Vertical Upward Air-Water Two-Phase Flow in an Annulus Channel J. J. Jeong(KAERI), B. Ozar, A. Dixit, T. Hibiki, M. Ishii(Purdue University) PDF보기 -
2007-Spring 제5분과 원자력안전 New Unheated Cold Wall Correction Factor KangHoon Kim, HongJu Kim, JongSeon Lim, SeungGeun Yang, EungJun Park(KNFC) PDF보기 -
2007-Spring 제5분과 원자력안전 Experimental Study on the Condensation Heat Transfer with Non-condensable Gas at High Pressure Hyoung-Kyoun Ahn, Yeon-Gun Lee, Jong-Won Kim and Goon-Cherl Park(SNU) PDF보기 -
2007-Spring 제5분과 원자력안전 FLB Mass and Energy Release Analysis for Kori 1 T. M. Kim, J. H. Choi, M. T. Oh, C. W. Kim(KOPEC) PDF보기 -
2007-Spring 제5분과 원자력안전 Estimation of the Thermal Diffusion Coefficient for the Hybrid Mixing Vane Y.J. Choo, K.H. Kang , S. H. Shin, Y. J. Youn, S.K. Moon, S.Y. Chun(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Effect of Tube Diameter on Heat Transfer to Vertically Upward Flowing Supercritical CO2 Deog Ji Kang, Sin Kim(CNU), Yoon Yeong Bae, Hwan Yeol Kim, Hyungrae Kim(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Thermal Conductivity Measurement and Heat Transfer Investigation of TiO2 and Al2O3 Nanofluids Shin Yoo, Jae Young Lee, and Man Woong Kim(HDU) PDF보기 -
2007-Spring 제5분과 원자력안전 Effects of the improved surface wettability and capillarity of nanoparticle deposition layer on CHF enhancement in pool boiling of nanofluids HyungDae Kim, MooHwan Kim(POSTECH) PDF보기 -
2007-Spring 제5분과 원자력안전 Development of Coupled Lattice Boltzmann and Finite Element Method for Fluid-Structure Interaction Problems in Commercial Nuclear Power Plants Kyung Wan Roh, Jong Chull Jo(KINS), and Young Kwon(NPS) PDF보기 -
2007-Spring 제5분과 원자력안전 Analysis of Flow-Induced Vibration Considering the Gap between Steam Generator Tube and Tube Support K. H. Lee, Y. J. Kim(GNEC), C. Y. Park(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Design Modification of Kori Unit 1 for the Equipment Qualification J.W. Park, M.Y. Kim, K.T. Han, J.D. Park(KOPEC) PDF보기 -
2007-Spring 제5분과 원자력안전 A Theoretical Method to Predict Wear of Plugged Tubes of Steam Generators Huinam Rhee(SNU), Ki-Wahn Ryu(CNU), Chi Yong Park(KEPRI) PDF보기 -
Last Modified : 1998-Autumn