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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Computation of Pressure Drop in Cross-flow through an In-line Tube Bundle Youngmin Bae, Yu Mi Jeon, Yeong-Gil Kim, Seung Heon Yang, Han-Ok Kang, Young-In Kim, Cheon-Tae Park, PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Effect of Core Residual Heat on Success Criteria during the Shutdown and Low Power Operation Moon-Oh Kim and Hee-Do Lee(ACT Co., Ltd.) Goon-Cherl Park(SNU) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Simulation of PAFS Using the CUPID Code Lee, Seung-Jun, Cho, Hyoung Kyu, and Yoon, Han Young(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Natural Circulation Cooldown Analysis for APR 1400 Using the SPACE Code Il Soon Park, Myung Taek Oh, Chan Eok Park, and Jong Joo Sohn(KEPCO E&C) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Study on Methodology for Establishment of the Minimum Allowable Fuel Channel Flow Rate in Steady State In Young Kim, Yong Won Choi, and Un Chul Lee(SNU) Kap Kim(KINS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Calculation of Turbulent and Thermal Mixing in a T-Junction: Comparison with Vattenfall Experimental Data Dong-Gu Kang and Kwang-Won Seul(KINS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Cross Flow Characteristics of the Core Simulator in SMART Reactor Flow Distribution Test Facility J. Yoon, Y. I. Kim, Y. J. Chung, and W. J. Lee(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Estimation of Porous Media Approach for Thermal Hydraulics of Nuclear Fuel Assembly Byung Soo Shin, San Kyu Lee, Yong Bum Bae, Nam Seok Kim, and Oh Hyun Keum(KINS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Study on the Secondary Thermal Power Reduction Factor of KSNP Cha. Hyeng Ho(KHNP) Lee. Kyoong Jin(CSU) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simulation of High Burn-up Fuel Cladding and ts Safety Assessment under LOCA Condition Dong Jun Park, Sung Bin Won, Byoung Kwon Choi, Jeong Yong Park, and Yang Hyun Koo(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Sensitivity Study for Coolant Void Reactivity Uncertainty Evaluation Huichang Yang and Young Ho Lee(L4S ENG) Kap Kim and Kwang-won Seul(KINS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of MARS-KS Codes on Counter Current Flow Limiting Sung-Han Lee, Yeon-Seung Kim, Won-Joon Chang,and Kwang-Won Seul(KINS) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Analysis on the Core Inlet Flow Similarity between an 1/20 Re Model and SMART Y. I. Kim, Y. M. Jeon, Y. G. Kim, Y. M. Bae, C. T. Park, and S. Choi(KAERI) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Analysis for the Effect of Mixing Vane Shape on TDC Kang Hoon Moon, Ho Young Park, Kang Hoon Kim, Eung Jun Park, and Jung Min Suh(KEPCO NF) PDF보기 -
2011-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Tong Axial Power Shape Factor Characteristics according to Parameters Euijae Kim, Ho Young Park, Kang Hoon Kim, and Eung Jun Park(KEPCO NF) PDF보기 -
Last Modified : 1998-Autumn