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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 Case Study of PHWR ROP Thermal Hydraulic Calculation Methodology Eui-Seung Ryu, Sung-Tae Yang, and Kyung-Ho Roh(KHNP) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis the PORV Accident for the Kori #2 Using SPACE Code Bum-Soo Youn, Hwang-Yong Jun, Dong-Hyuk Lee, Se-Yun Kim, and Sang-Jun Ha(KEPCO RI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis of ATLAS 6-inch Cold Leg Break Simulation with MARS-KS Code Seyun Kim, Hwang-Yong Jun, and Sang-Jun Ha(KEPCO RI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simulation of the VISTA SG Heat Transfer Experiment Using MIDAS/SMR Jong-Hwa Park, Dong-Ha Kim, Young-Jong Chung, and Sunhee-Park(KAERI) Seong-Won Cho(KORTIC) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) LOFT L9-3 ATWS Experiment Simulation Using the SPACE Code Chang-Keun Yang, Dong-Hyuk Lee, Yo-Han Kim, and Sang-Jun Ha(KEPCO RI) Sung-Yull Hong(YU) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Numerical Simulation for a Core Simulator of ACOP Jun Ho Bae, Dong Jin Euh, and Tae-Soon Kwon(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Analysis for the Variation of Flow Pattern between the Real Model with Holes and Simplified Model with Porous in Steam Generator Y. G. KIM, Y. M. JEON, Y. M. BAE, Y. I. KIM, C. T. PARK, and S. CHOI(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Verification of FAST Code Using Method of Manufactured Solution Hyuk Kwon, K. W. Seo, S. J. Kim, J. H. Cha, T. W. Kim, and D. H. Hwang(KAERI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Pressurizer Heater and Safety Valve Test for SPACE Code Dong-Hyuk Lee, Bum-Soo Youn, Hwang-Yong Jun, Se-Yun Kim, and Sang-Jun Ha(KEPCO RI) PDF보기 -
2011-Spring 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis on a Fuel Assembly Simulator in the Reactor Flow Distribution Test for SMART Y. I. Kim, Y. M. Jeon, J. Yoon, H. Bae, Y. J. Chung, and W. J. Lee(KAERI) PDF보기 -
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 -
Last Modified : 1998-Autumn