학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2008-Spring | 제10분과 : 원자력 계측제어 및 자동원격-Poster(Nuclear I&C and Automatic Remote Systems) | Application of 4-Face Fuel Visual Inspection System during Outage in Nuclear Power Plant | J. C. Shin, J. I. Kim, C. B. Choi, and Y. C. Kim (KNF) C. B. Kang (KHNP) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | The Evaluation of Impact Strength of IFM Support Grid and its Experimental Verification | Soobum Lee and Keenam Song (KAERI) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | Application of CASMO-3/MASTER Code System to the OPR1000 | Guk Jong You, Jung Hoon Sim, and Han Gon Kim (KHNP) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | Core Design of a 1200 MWe Sodium Cooled Fast Reactor by Using Non-Fuel Rods | Ki-Bog Lee, Hyung-Kook Joo, Jae-Woon Yoo, and Yeong-il Kim (KAERI) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | Comparison of Three-Dimensional Thermal-Hydraulic Characteristics Between 7-pin and 19-pin Wire-Wrapped Fuel Assemblies | Wasim Raza and Kwang-Yong Kim (IHU) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | Influence of Nuclear Data Files on the Analyses of Metallic Uranium Fueled BFS Critical Assemblies | Jaewoon Yoo, Yeong-Il Kim, and Hoon Song (KAERI) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | The GAMMA Code Assessment of the HTR-10 Safety Demonstration Experiments-LOFC ATWS | Ji Su Jun, HongSik Lim, and Won-Jae Lee (KAERI) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | Development of a Spark Ignition Model for a CFD Analysis of the JAEA Explosion Test | H. S. Kang, S. B. Kim, M. H. Kim, and W. J. Lee(KAERI) H. C. No (KAIST) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | CFD Analysis on the Prismatic Fuel Assembly of a Very High Temperature Reactor | Nam-il Tak, Min-Hwan Kim, and Won-Jae Lee (KAERI) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | Thermal-Fluid Analysis of the Local Hot Core Region in a Pebble-Bed Reactor | Min-Hwan Kim, Hong-Sik Lim, and Won-Jae Lee (KAERI) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | Stress Concentration Evaluation of RV Capped CEDM Nozzle Threaded Joint and Omega Seal in APR1400 | Jung-Dae Son, Se-Hun Kim, Ji-Hyun Kim, and Moon-Kil Park (Doosan Heavy Co.Ltd) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | Analysis of Turbulent Heat Transfer Downstream of Mixing Vanes with Tip in Subchannel of Nuclear Reactor | Dong-Yoon Shin and Kwang-Yong Kim (IHU) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | Heat Transfer Experiment in an Integrated Single-Region for the IHTS Simplification in a LMR | Jong-Hyeun Choi, Kyeong-Chae Jeong, Byoung-Hae Choi, and Byung-Ho Kim (KAERI) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | Conceptual Core Designs with a Variant Thickness Clad or Enrichment-Split Fuel for a 1200MWe Sodium Cooled Fast Reactor | Hyung-Kook Joo, Ki-Bog Lee, Jae-Woon Yoo, and Yeong-Il Kim (KAERI) | PDF보기 | - | ||
| 2007-Autumn | 제1분과 : 원자로시스템기술(Nuclear System Technology) | Conceptual Design of a Co-axial Structure Applicable to an Intermediate Heat Exchanger of a Pool-type Sodium-Cooled Fast Reactor | Chang-Gyu Park, Jong-Bum Kim, Hyeong-Yeon Lee, and Jae-Han Lee (KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
