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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Droplet Size and Velocity Measurement in a 2¡¿2 Subchannel for the Reflood Heat Transfer Experiment H. K. Cho, S. Cho, K. Y. Choi, and C. H. Song(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Sensitivity Study on Thermal Hydraulic Parameters of Research Reactor with Plate Type Fuel Chae Heetaek, Park Jonghark, and Park Cheol(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Computation of the Temperature Distribution in a Fuel Particle Bed in Single and Two Phase Conditions Eui Kwang Kim, Chung Ho Cho, and Yong Bum Lee(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) IRWST Water Temperature Distribution Analysis during POSRV Actuation I. S. Yeo, Y. T. Moon, and K. K. Woo(KOPEC) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Design of a MAAP Specific Scenario Input Generation Module for a Systematic Analysis of Severe Accident Progression Ko-Ryu Kim, Yong-Man Song, Soo-Yong Park, and Kwang-Il Ahn(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Performance Evaluation of a Hot Water Layer Using a Numerical Simulation Jonghark Park, Heetaek Chae, Heonil Kim, Byungjin Jun, and Cheol Park(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Study on Primary Heat Transport and ECC System Behavior in Large LOCA for CANDU NPP Kim Yun Ho, Park Dong Hwan, and Choi Hoon(KEPRI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) CHF Enhancement in Flow Boiling System with TSP and Boric Acid Solutions under Atmospheric Pressure Juno Lee, Yong Hoon Jeong, Byungsoo Shin, and Soon Heung Chang(KAIST) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Status of SPACE Safety Analysis Code Development Dong Hyuk Lee, Chang Keun Yang, Seyun Kim, and Sang Jun Ha(KEPRI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preparation of Input Deck to Analyze the Nuclear Power Plant for the Use of Regulatory Verification Doohyuk Kang, Hyungseok Kim, and Jaeseung Suh(ENESYS) Seunghoon Ahn and Yongjin Cho(KINS) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Comparisons of MARS Code Analysis Results on DVI Line Break LOCAs at Different Break Sizes between SNUF and the APR1400 for Sensitivity Studies X. G. Yu, K.H. Lee, and G. C. Park(SNU) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Study on Heat-up Phenomena of the RHR Pump Room in KORI Units 2 for the Loss of HVAC Accidents Churl Yoon, Jinhee Park, Ho Gon Lim, and Sang Hoon Han(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of Off-take Model, Subcooled Boiling Model, and Radiation Heat Transfer Input Model into the MARS Code for Regulatory Auditing of CANDU Reactors C. Yoon, B. W. Rhee, and B. D. Chung(KAERI) S. H. Ahn and M. W. Kim(KINS) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) NUCIRC Single Channel Analysis for Calculating the Power Coefficients of the Wolsong Unit 1 Churl Yoon, Ji Su Jun, and Joo Hwan Park(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Thermal-hydraulic Potential of Dual Cooled Annular Fuel for OPR-1000 Tae-Hyun Chun, Chang-Hwan Shin, Wang-Kee In, and Dong-Suck Oh(KAERI) PDF보기 -
Last Modified : 1998-Autumn