학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Temperature Effect on the Radiation-Corrective Gas Temperature Measurement | Chan Soo Kim, Sung-Deok Hong, and YongWan Kim(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Progress in the Performance Verification of PCHE Type Na-CO2Heat Exchanger | Jieun Kim, Soo Jae Kim, Eunho Kim, and Moo Hwan Kim(POSTECH) J.E.Cha and S.O.Kim(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | VHTR Thermal Fluids PIRT Development Based on the Previous PIRTs Developed by Licensee and Regulatory Authority | Su Hyun HWANG, Seong Su JEON, Soon Joon HONG, and Byung Chul LEE(FNC Tech.) Chang Wook HUH and Chang | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Design of Helium Brayton Cycle for Small Modular High Temperature Gas cooled Reactor | Ahn. Yoonhan, Lee. Jekyoung, and Lee. Jeong Ik(KAIST) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Porosity of Nuclear Gade Graphite | Eung-Seon Kim, Ji-Seon Song, Sung-Deok Hong, and Yong-Wan Kim(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Simulation of Bunsen Reaction with Electro-dialysis for Efficient Phase Separation | Jun Kyu Park, Shripad T. Revankar, and Jae Sung Lee(POSTECH) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Whole Core Thermal-hydraulic Design of a Sodium Cooled Fast Reactor Considering the Gamma Energy Transport | Sun Rock Choi, Min-Ho Back, Wonseok Park, and Sang-Ji Kim(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Safety Evaluation of UCFR-1000 MWe with MATRA-LMR | Han Seo, Sarah Kang, and In Cheol Bang(UNIST) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Determination of the Pipe Diameter and Length of a Sodium Experimental Installation for Single Phase Natural Convection Simulations | Dongsup So and Yong Bum Lee(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Natural Circulation Test of the KALIMER-600 Water Scaled Model | JaeEun Cha and SeongO Kim(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | A Safety Function Evaluation of the Advanced Sodium-cooled Fast Reactor in a Loss of Heat Sink Accident | Kwi Lim Lee, Kwi Seok Ha, Hae Yong Jeong, Won Pyo Chang, Seok Hun Kang, and ChiWoong Choi(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Evaluation of Flow-guide Effects in a Sodium-cooled Pool Type Reactor | Ji-Woong Han, Jae-Hyuk Eoh, Seong-O Kim, and Tae-Ho Lee(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Multi-dimensional Approach of MARS-LMR for the Analysis of Phenix End-of-Life Natural Circulation Test | Hae-Yong Jeong, Kwi-Seok Ha, Won-Pyo Chang, and Kwi-Lim Lee(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Simulation of Phenix EOL Asymmetric Test | Kwi-Seok Ha, Kwi-Lim Lee, Chi-Woong Choi, Seok-Hun Kang, Won-Pyo Chang, and Hae-Yong Jeong(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Evaluation of Pressure Loss and Heat Transfer Correlations for Design of the IntermediateHeat Exchanger in a Sodium Cooled Fast Reactor | Seok-Ki Choi, Seong-O Kim, and Tae-Ho Lee(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
