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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) A Response Surface Method for the VHTR Optimization Design Chan Suh Lee, Hyung Suk Lee, and Moo Sung Jae(HYU) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Relaxation of Pressure and Temperature during HELBA for Subcompartment Dong-Soo Song, Jeong-Kwan Suh, Duk-Joo Yoon, and In-Hwan Kim(KEPCO RI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simulation of the QUEOS Experiment Using Rigid Dynamic-moving Particle Semi-implicit (RD-MPS) Method Shane Park(KEPCO NF) Hyun Sun Park(SINEWSTEK) Gyoodong Jeun(HYU) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Analysis of Hydraulic Characteristics for a PWR Fuel Assembly Dong-Hyeog Yoon, Han-Chul Kim, and Kwang-Won Seul(KINS) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Heat Transfer Correlation Dependency on Thermal Load Response of a Melting Pool in a Lower Plenum during Severe Accident Jae Ryong Lee, Rae Joon Park, and Seong Wan Hong(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis of a Natural Circulation in the Reactor Coolant System Following a High Pressure Severe Accident at APR1400 Han-Chul Kim, Yong-Jin Cho, and Jae-Hong Park(KINS) Song-Won Cho(KORTIC) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Triggerability and Explosion Potential at Fuel Coolant Interactions Ik Kyu Park, Jong Hwan Kim, and Seong Wan Hong(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Verification of Severe Accident Management Strategy Based on CANDU Reactor Young Choi, D. H. Kim, S. D. Kim, S. Y. Park, and Y. H. Jin(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) PCTRAN Analysis of Fukushima Event Li-Chi Cliff Po(MST) Juyoul Kim(FNC Tech.) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis of Air-water Two Phase Flow for K-HERMES-HALF Experiment Using RELAP5/MOD3 Rae-Joon Park, Kwang-Soon Ha, Sang-Baik Kim, and Seong-Wan Hong(KAERI) Sun Heo(KHNP) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Geometry and Material Scaling on Two Phase Natural Circulation Flow for K-HERMESHALF Experiment Rae-Joon Park, Kwang-Soon Ha, Sang-Baik Kim, and Seong-Wan Hong(KAERI) Sun Heo(KHNP) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) MCCl Simulation for the APR-1400 TLOFW Sequence Jong-Hwa Park, Hwan Yeol Kim, Seong Wan Hong, and Kwang Soon Ha(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Severe Accident Analysis of SBLOCA Sequences for SMART Using MELCOR Code Jaecheol Kim and Gunhyo Jung(FNC Tech.) Hanchul Kim(KINS) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of Assessment Methodology of Chemical Behavior of Volatile Iodide under Severe Accident Conditions Using EPICUR Experiments Jae Yong Oh and Jong-Il Yun(KAIST) Do Sam Kim and Han-Chul Kim(KINS) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Comparison of Severe Accident Scenarios for an Advanced PWR Using MELCOR Codes Tae-Woon Kim, Jin-Ho Song, and Sung-Won Cho(KAERI) PDF보기 -
Last Modified : 1998-Autumn