학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Effect of Core Bypass Flow During 6 Inch Cold Leg SBLOCA Test with the ATLAS | Seok Cho, Ki-Yong Choi, Hyun-Sik Park, Kyoung-Ho Kang, Yeon-Sik Kim, Nam-Hyun Choi, Bok-Duk Kim, and | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Localization of the Hot Spot in the Gap of Pebble Bed of Very High Temperature Gas Cooled Reactor(VHTGR) | Sa-Ya Lee, Sung-Je Hong, and Jae-Young Lee(HGU) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Testing Supercritical Carbon Dioxide Flowing Up Vertical Tube | Byung J. Lee and Kune Y. Suh(SNU) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Localization of Ultra High Pressure and Temperature Using Methylene Blue Oscillation under Pressure Radiation | Sung-Je Hong, Jung-Uen Kim, Joo-Han Bae, and Jae-Young Lee(HGU) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 3-Dimensional Fluid Dynamics Analysis of Bypass Flow in Sub-channel with Crept Pressure Tube by Aged CANDU Reactor | Tae Kwang Eom, Sung Je Hong, and Jae Young Lee(HGU) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Verification of the SPACE Code Using Conceptual Test Problems | Myung Taek Oh, Chan Eok Park, and Gyu Cheon Lee(KOPEC) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | An Improved Numerical Scheme to Calculate the Pressure Gradient on Unstructured Meshes for Two-Phase Flows | Heedong Lee(KAIST) Jae Jun Jeong, Hyoung kyu Cho, and Han Young Yoon(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Staggered Mesh for the SPACE Code and its Application to the System Construction | Chan Eok Park, Sang Yong Lee, and Eun Kee Kim(KOPEC) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Advanced Wall Boiling Model with Wide Range Applicability for the Subcooled Boiling Flow and its Application into the CFD Code | B. J. Yun, and C.-H. Song(KAERI) A. Splawski and S. Lo(CD-Adapco) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Fundamental Validation of the SPACE code: Basic Hydraulics | Byoung Jae Kim, Moon Kyu Hwang, Kyoung Doo Kim, and Seung Wook Lee(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A Brief Review on the Baer-Nunziato Type Multi-pressure Multi-fluid Models | Sang Yong Lee, Chan Eok Park, and Gyu Cheon Lee(KOPEC) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Development of Two-Dimensional Void Profile Measurement Technique Using Impedance | J. H. Bae and J. Y. Lee(HGU) D. J. Euh, S. Kim, B. D. Kim, W. M. Park, B. J. Yun, C. -H. Song, and K | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | CFD Calculation of Turbulent and Thermal Mixing in a T-Junction: OECD/NEA Sponsored CFD Benchmark Exercise | Dong Gu Kang, Kwang Won Seul, and Yong Ho Ryu(KINS) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Simulation of the Downcomer Boiling Test with the Component Thermal Hydraulic Analysis Code CUPID | H. K. Cho, B. J. Yun, I. K. Park, and J. J. Jeong(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | CHF Enhancement in Flow Boiling using Al O Nano-Fluid and Al O Nano-Particle Deposited Tube | Tae Il Kim, T. H. Chun, and S. H. Chang(KAIST) | PDF보기 | - |
Last Modified : 1998-Autumn
