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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Survey of Core Inlet Blockage Test Due to Debris after Large Break LOCA Jae Yong Lee, Moon Gyu Park, and Jeong Kwan Suh(KHNP CRI) Seung Jong Oh(KINGS) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Approach to Reducing the Adverse Effect of Inappropriate Human Actions in Nuclear Power Plant Jinkyun park, Wondea Jung, Jaewhan Kim, Seunghwan Kim, and Sun Yeong Choi(KAERI) Gyunyoung Heo(KHU) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Manual Fire Fighting Tactics at Nuclear Power Plant Moon-Hak Jee and Chan-Kook Moon(KHNP CRI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) FDS5 Simulation of PRISME INTEGRAL Test, PRS_INT_4 JongSeuk PARK(KINS) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simulation of Iodine Behavior by Coupling of a Standalone Model with MELCOR Han-Chul Kim(KINS) Song-Won Cho(KORTIC) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Design Modification of Sparger in the IRWST Sang-Nyung Kim and Seung-Won Han(KHU) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Integrated Passive Safety System (IPSS) for Ultimate Safe Nuclear Power Plants Soon Heung Chang, Sang Ho Kim, and Jae Young Choi(KAIST) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) On the Consistency of Non-drag Interfacial Force Models in Fully Developed Turbulent Bubbly Two Phase Flow Van Thai Nguyen, Chul-Hwa Song, Byoung-Uhn Bae, and Dong Jin Euh(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Computational Fluid Dynamic Analysis of Alumina Nanofluid Coolant for a Typical PWRs Mohammad Nazififard and Kune Y. Suh(SNU) Mohammad Reza Nematollahi(Shiraz Univ.) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simulation of Two-phase Natural Circulation Loop for Core Cather Cooling Using Air Water S. T. Revankar, S.F. Huang and K.W. Song(POSTECH) B.W Rhee, R.J. Park, and J.H. Song(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Simulation of Acoustic-induced Vibration in Main Steam Line of APR1400 Sang-Gyu Lim, Tae-Jun Kim and Han-Gon Kim(KHNP CRI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Core Pressure Drop Characteristics in a CANDU Reactor Jun Ho Bae, Bo Wook Lee and Jong Yeob Jeong(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis of MSLB for SKN 5&6 Containment Design Using KIMERA Methodology Cheol Woo Kim, Seoung Rae Kim, and Ki Moon Park(KEPCO E&C) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Post-test Calculation of a Feedwater Line Break Experiment Performed at ATLAS XinGuo Yu, Hyun Sik Park, and Ki Yong Choi(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Discussion on Scaling Analysis on the Fluid-solid Coupled Domain in Sodium Fast Reactor Soon Joon HONG and Doo Yong LEE(FNC Tech.) Jae Hyuk EOH(KAERI) PDF보기 -
Last Modified : 1998-Autumn