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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2005-Spring 제5분과 : 원자력안전-열수력 실험 Investigation on the Rewetting Temperature Behavior in a Vertical Annulus Geometry with Uniform and Cosine Power Distribution S.Cho,S.Y.Chun,B.D.Kim,J.K.Park,W.P.Baek (KAERI) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 Establishment of Safety Basis for Power Maneuvering in CANDU NPP Kim Yunho and Choi Hoon (KAERI) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 Evaluation of the Thermal-Hydraulic System Analysis Code for SMART-P Yong Won Choi,Dong Ju Jang,Chang Hwan Park,Un Chul Lee,(SNU) Young Dong Hwang,Kyu Hyung Lee,Hee Chul PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 Evaluation of TASS/SMR with steady state analysis of High Temperature/High Pressure Thermal-Hydraulic Test Facility (VISTA) Dong Ju Jang,Yong Won Choi,Chang Hwan Park,Un Chul Lee (SNU),Young Dong Hwang,Kyu Hyung Lee,Hee Chul PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 Self-Power-Regulating Characteristics of the KALIMER-150 Core during Unscrammed Accidents Young Min Kwon,Ki Seok Ha,Hae Yong Jeong,Won Pyo Chang,Yong Bum Lee (KAERI) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 CFD Prediction for an Asymmetric Behavior of the Thermal Mixing in a Subcooled Water Tank H.S.Kang,Y.S.Kim,H.G.Jun,Y.J.Youn,C.H.Song (KAERI) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 Maximum Allowable Power Levels in HANARO Fuel Channels Heetaek Chae,Choong Sung Lee,Jong Hark Park,Heonil Kim (KAERI) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 LBLOCA Accident Analysis for Wolsong Unit 1 Environmental Qualification Kim Jonghyun,Lee Kwangho,Kim Younho,Choi Hoon and Kim yongbae (KAERI) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 Thermal Flow Analysis for a Severe Cold-water Injection Transient Condition in the Purification System Line and the Heat Transport System Line Man Heung Park,Kwang Chu Kim,Hag Ki Youm (KOPEC),Sun Ki Lee,Seung Ryul Hong (KEPRI) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 Thermal Hydraulic Similarity Analysis of the ATLAS for Main Steam Line Break Accidents K.Y.Choi,D.J.Euh,T.S.Kwon,H.S.Park,W.P.Baek (KAERI) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 Evaluation of Natural Circulation Capability in KORI 1 and KORI 3&4 Yong Jin Cho,Sang Kyoon Lee,In Goo Kim (KINS),Chong Bae Lee (KHNP) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 In-Core LOCA (PTR) Analysis with Poisoned Moderator S.R.Kim,B.G.Kim,T.M.Kim,J.H.Choi (KOPEC),Yun-Ho Kim,Hoon Choi (KEPRI) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 Overview of Critical Flow Test Program for the Simulation of Loss of Coolant Accident and Preliminary Analysis of Test Results C.K.Park,H.S.Park,Y.J.Yoon,C.H.Song (KAERI) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 Simplified RETRAN Model for SGTR Analysis of Ulchin Unit 3/4 Dong Hyuk Lee,Jae Hwa Koh,Yo Han Kim,Chang Kyung Sung (KEPRI) PDF보기 -
2005-Spring 제5분과 : 원자력안전-열수력 실험 Critical Heat Flux of Vertical Upward Water Flow in Uniformly Heated Round Tube Sang-Ki Moon,Se-Young Chun,Jong-Kuk Park, Won-Pil Baek (KAERI) PDF보기 -
Last Modified : 1998-Autumn