학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2015-Spring | 1A : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 10:00 | 삼다홀A | In-Vessel Storage Cooling Analysis in PGSFR | Jung Yoon and Tae-ho Lee(KAERI) | PDF보기 | - |
| 2015-Spring | 1A : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 10:20 | 삼다홀A | Validation of Printed Circuit Heat Exchanger Design Code KAIST_HXD | Seungjoon Baik, Seong Gu Kim, Jekyoung Lee, and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2015-Spring | 1A : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 11:00 | 삼다홀A | Cooling Performance of ALIP according to the Air or Sodium Cooling Type | Huee-Youl Ye, Jung Yoon, and Tae-Ho Lee(KAERI) | PDF보기 | - |
| 2015-Spring | 1A : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 11:20 | 삼다홀A | Multidimensional Thermal-Hydraulic Analysis for Decay Heat Exchanger of PGSFR | Jonggan Hong, Jung Yoon, Dehee Kim, and Tae-Ho Lee(KAERI) | PDF보기 | - |
| 2015-Spring | 1A : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 11:40 | 삼다홀A | Design and Performance Evaluation of a Combined DHX Unit for SFR Design Application | Jaehyuk Eoh, Dehee Kim, Chang-Gyu Park, and Ji-Young Jeong(KAERI) | PDF보기 | - |
| 2015-Spring | 1A : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 12:00 | 삼다홀A | Visualization Study of Melt Dispersion Behavior for SFR with a Metallic Fuel under Severe Accidents | Hyo Heo, Seong Dae Park, and In Cheol Bang(UNIST) Dong Wook Jerng(CAU) | PDF보기 | - |
| 2015-Spring | 1B : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 09:00 | 삼다홀 B | Heat Transfer Distribution for Reactor Cavity Cooling System Riser Considering Thermal Conduction | Byung Ha Park(KAERI) | PDF보기 | - |
| 2015-Spring | 1B : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 09:20 | 삼다홀 B | Simulation on the HTTR Control Rod Withdrawal Test | Ji Su Jun, Nam-il Tak, and Hong Sik Lim(KAERI) | PDF보기 | - |
| 2015-Spring | 1B : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 09:40 | 삼다홀 B | Preliminary Analysis of the KAERI RCCS Experiment Using GAMMA+ | Samukelisiwe Khoza, Nam-il Tak, Hong-Sik Lim, Sung-Nam Lee, Bong-Hyun Cho, and Jong-Hwan Kim(KAERI) | PDF보기 | - |
| 2015-Spring | 1B : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 10:00 | 삼다홀 B | Low Cycle Fatigue Behavior of Alloy 617 Base Metal and Welded Joints at Room Temperature and 850˚C for VHTR Applications | Seon Jin Kim and Rando T. Dewa(PKNU) Woo Gon Kim and Min Hwan Kim(KAERI) | PDF보기 | - |
| 2015-Spring | 1B : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 10:20 | 삼다홀 B | Heat Transfer Experiments on an Internally Insulated Hot-Gas-Duct | SungDeok Hong, ChanSoo Kim, and MinHwan Kim(KAERI) InJun Lee and JaeSool Shim(YU) | PDF보기 | - |
| 2015-Spring | 1B : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 11:00 | 삼다홀 B | Oxidation Protective SiC Coating on Graphite for VHTR Core Support Structure | Jae-Won Park, Eung-Seon Kim, and Jae-Un Kim(KAERI) William E. Winde(INL) | PDF보기 | - |
| 2015-Spring | 1B : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 11:20 | 삼다홀 B | Comparison of Damage Formation and Crack Propagation Behavior of Selected Nuclear Graphite for HTGR | Se-Hwan Chi, Hyun-Ju Kim, Eung-Seon Kim, and Min-Hwan Kim(KAERI) | PDF보기 | - |
| 2015-Spring | 1B : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 11:40 | 삼다홀 B | High Temperature Operational Experiences of Helium Experimental Loop | Chan Soo Kim, Sung-Deok Hong, Eung-Seon Kim, and Min Hwan Kim(KAERI) | PDF보기 | - |
| 2015-Spring | 1B : 원자로시스템기술(Reactor System Technology) | 5.7(Thu) 12:00 | 삼다홀 B | Experimental Study for Flow Regime of Downward Air-Water Two-Phase Flow in a Vertical Narrow Rectangular Channel | T.H. Kim, B.J. Yun, and J.H. Jeong(PNU) | PDF보기 | - |
Last Modified : 1998-Autumn
