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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Application of a New Approach for Estimating LOCA and SGTR Frequencies Ho-Jun Jeon, Ji-Yong Oh, and Moon-Goo Chi(KHNP) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Evaluation of the Unexpected Trip Limits Using the Quality Control Approach Hyun-woo Lee and Moosung Jae(HYU) Kilyoo Kim(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Thermal Field of Moderator Circulation in CANDU-6 Reactor Tae Kwang Eom, Sung Je Hong, and Jae Young Lee(HGU) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of MARS Code on CHF with Fluid-to-Fluid Method Under Inlet Flow Fluctuation Jin S. Hwang, Jong W. Kim, and Goon C. Park(SNU) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simulation of UPTF Test 20 by Using MARS Multi-Dimensional Component Sung Won Bae and Bub Dong Chung(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Transport Characteristics of Representative Debris in a Open Channel Kyung Sik Choi and Ji Hwan Joeng(PNU) Joo Yeop Park(KINS) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) MARS Transient Analyzer for Dual Reactor Unit Producing 2000 MWe Kyoung M. Kang and Kune Y. Suh(SNU) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Experimental Validation of a Thermal-hydraulic Analysis Code for REX-10 Yeon-Gun Lee, Jong-Won Kim, and Goon-Cherl Park(SNU) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Test for Constitutive Models of CAP Yeon Joon Choo, Soon Joon Hong, Su Hyun Hwang, Keo Hyung Lee, Min Ki Kim, and Byung Chul Lee(FNC Tec PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Upwind Scheme and Local Head Model in CAP Soon Joon Hong, Su Hyun Hwang, Yeon Joon Choo, Keo Hyung Lee, Min Ki Kim, and Byung Chul Lee(FNC Tec PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Integral Effect Test Program for SMART Design using the VISTA ITL Facility Hyun-Sik Park, Ki-Yong Choi, Seok Cho, Yeon-Sik Kim, Nam-Hyun Choi, Kyoung-Ho Min, Yong-Chul Shin, Y PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Design of Steam Generator for SMART ITL Hwang Bae, Hyun-Sik Park, Sung-Jae Yi, and Sang-Ki Moon(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Construction of Experimental Facility for SMART Flow Mixing Header Assembly Jong-Soo Choi, Jong-Won Kim, and Goon-Cherl Park(SNU) Young-In Kim(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Systematic Application of the AtomCARE Real-time Plant Information to support Severe Accident Response Activities Do Sam Kim and Key Yong Sung(KINS) Kwang-IL Ahn(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Effect of External Vessel Cooling for a 2 Inch LOCA Severe Accident Scenario at SMART with MIDAS/SMR Jong-Hwa Park, Dong-Ha Kim, Young-Jong Chung, and Sunhee Park(KAERI) Seong-Won Cho(KORTIC) PDF보기 -
Last Modified : 1998-Autumn