학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2015-Spring | 5F : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 11:00 | 400 | Review of Mixed Convection Flow Regime Map of a Vertical Pipe | Myeong-Seon Chae and Bum-Jin Chung(KHU) Gyeong-Uk Kang(KORAD) | PDF보기 | - |
| 2015-Spring | 5F : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 11:20 | 400 | Similarity Analysis for Reactor Flow Distribution Test and Its Validation | Soon Joon HONG and Jung Hui HA(FNC Tech.) Taehoo LEE and Ji Woong HAN(KAERI) | PDF보기 | - |
| 2015-Spring | 5F : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 11:40 | 400 | Thermal Performance and Operation Limit of Heat Pipe Containing Neutron Absorber | Kyung Mo Kim, Yeong Shin Jeong, In Guk Kim, and In Choel Bang(UNIST) | PDF보기 | - |
| 2015-Spring | 5F : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 12:00 | 400 | Isothermal Flow Measurement Using Planar PIV in the 1/4 Scaled Model of CANDU Reactor | Sunghyuk lm and Hyung Jin Sung(KAIST) Han Seo and In Cheol Bang(UNIST) Hyoung Tae Kim(KAERI) | PDF보기 | - |
| 2015-Spring | 5F : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 12:20 | 400 | CHF Enhancement by Surface Patterning Based on Hydrodynamic Instability Model | Han Seo and In Cheol Bang(UNIST) | PDF보기 | - |
| 2015-Spring | 5G : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 09:00 | 401A | The Safety Assessment of OPR-1000 for Station Blackout Applying Combined Deterministic and Probabilistic Procedure | Dong Gu Kang, Seung-Hoon Ahn, and Dae-Hyung Cho(KINS) | PDF보기 | PPT보기 |
| 2015-Spring | 5G : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 09:20 | 401A | Thermodynamic Optimization of Supercritical CO2 Brayton Cycles | Dong-Ryul Rhim, Sung-Ho Park, Su-Hyun Kim, and Choong-Sub Yeom(IAE) | PDF보기 | - |
| 2015-Spring | 5G : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 09:40 | 401A | Performance Evaluation of the Concept of Hybrid Heat Pipe as Passive In-core Cooling Systems for Advanced Nuclear Power Plant | Yeong Shin Jeong, Kyung Mo Kim, In Guk Kim, and In Cheol Bang(UNIST) | PDF보기 | - |
| 2015-Spring | 5G : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri)10:00 | 401A | An Overall Investigation of Cold Leg Pipe Break Accidents of the ATLAS Facility | Yeon-Sik Kim, Seok Cho, Ki-Yong Choi, and Bok-Deuk Kim(KAERI) | PDF보기 | - |
| 2015-Spring | 5G : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 10:20 | 401A | Development of TPNCIRC Code for Evaluation of Two-Phase Natural Circulation Flow Performance under External Reactor Vessel Cooling Conditions | A-Reum Choi, Hyuk-Jin Song, and Jong-Woon Park(DU) | PDF보기 | - |
| 2015-Spring | 5G : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 11:00 | 401A | Safety Injection System Filling Using Dynamic Venting | Sung Je Hong, Wong Bae Kim, Jin Huh, Joo Hee Lee, In Young lm, and Eun Kee Kim(KEPCO E&C) | PDF보기 | - |
| 2015-Spring | 5G : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 11:20 | 401A | Analysis on Roles for Components of Passive Emergency Core Cooling System | Soon II Chung and Soon Joon Hong(FNC Tech.) Sang Hee Kang and Han Gon Kim(KHNP) | PDF보기 | - |
| 2015-Spring | 5G : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 11:40 | 401A | Preliminary Analysis of Supercritical CO2 Loop Using MARS | Jai Oan Cho and Jeong lk Lee(KAIST) | PDF보기 | - |
| 2015-Spring | 5G : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 12:00 | 401A | Thermohydraulic Design Analysis Modeling for Korea Advanced NUclear Thermal Engine Rocket for Space Application | Seung Hyun Nam, Jae Young Choi, Paolo F. Venneri, Yong Hoon Jeong, and Soon Heung Chang(KAIST) | PDF보기 | - |
| 2015-Spring | 5H : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 5.8(Fri) 09:00 | 401B | Statistical Uncertainty Quantification of Physical Models during Reflood of LBLOCA | Deog Yeon Oh, Kwang Won Seul, and Sweng Woong Woo(KINS) | PDF보기 | - |
Last Modified : 1998-Autumn
