학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 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 | - | ||
| 2005-Spring | 제5분과 : 원자력안전-열수력 실험 | Optimization of Flow Rate in Lead-Bismuth Target System with Dual Injection Tube | C.H.Cho,Y.Kim,T.Y.Song (KAERI) | PDF보기 | - | ||
| 2005-Spring | 제5분과 : 원자력안전-열수력 실험 | Thermal Hydraulic Analyses of Lead-Bismuth Spallation Target System with due regard to Core Temperature Distribution | C.H.Cho,Y.Kim,T.Y.Song (KAERI) | PDF보기 | - | ||
| 2005-Spring | 제5분과 : 원자력안전-열수력 실험 | Flow Induced Vibration Characteristics in 2X3 Bundle Critical Heat Flux experiment | Dae Hun Kim,Soon Heung Chang (KAIST) | PDF보기 | - | ||
| 2005-Spring | 제5분과 : 원자력안전-열수력 실험 | Stability Enhancement of Swing Check Valve Model | Ho-Gon Lim,Jin-Hee Park,Seung-Chul Jang (KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
