학술발표회 논문집 (ISSN: 3140-1864)
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2007-Spring | 제1분과 원자로기술 | Analysis of a Transient Over-Power in KALIMER-600 | Hae-yong Jeong, Kwi-seokHa, Young-min Kwon, Won-pyo Chang, and Yong-bumLee (KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | Preliminary Crack Effects Analysis of the Metal Fuel for SFR | Byoung Oon Lee, Jin SikCheon, and Chan Bock Lee(KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | Simulation of SHRT-17 Test Using SSC-K | Kwi-Seok Ha, Hae-YoungJeong, Young-Min Kwon,Won-pyo Chang, and Yong-Bum Lee (KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | CFD Study of the Active Part of the HYPER LBE Spallation Target System | Chungho Cho, Nam-il Tak,and Yong-Bum Lee (KAERI)Jae-Hyuk Choi (SNU) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | The MHD Pressure Drop by Transverse Magnetic Field on a Liquid Sodium Flow | Hee Reyoung Kim, Jae EunCha, Jong Man Kim, and HoYoon Nam (KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | The Heat Transfer Characteristics in the Radially Separated DTBSG | Bo Young Choi, Seyun Kim,Jae-Hyuk Eoh, Eui KwangKim, Jong-Hyun Choi, andSeong-O Kim (KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | Recent Development of the Inter-Assembly Flow Analysis Tools for SFR Core Thermal Hydraulics | Y. G. Kim, E. K. Kim, and Y. B.Lee (KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | Development of the On-line Acoustic Leak Detection Tool for the SFR Steam Generator Protection | Tae-Joon Kim, Ji-YoungJeong, Jong-Man Kim, and Byung-Ho Kim (KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | Flow Grouping Study for KALIMER-600 Single Enrichment Core with Varying Fuel Clad Thickness | Y. G. Kim, S. G. Hong, and Y.B. Lee (KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | ODS F/M Steels for the Application to SFR Fuel Cladding | J. H. Baek, S. M. Peng, T.K.Kim, S.H. Kim, and C.B. Lee(KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | Thermal Hydraulic Analysis of a Doulde Tube Bundle Steam Generator Using a Numerial Method | Eui-Kwang Kim, Y.-G. Kim,Won-pyo Chang, and Youg-Bum Lee (KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | Comparisons of Fission Rate Distributions with Experimental Data | Hoon Song, Young In Kim,and Yeong Il Kim (KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | KALIMER-600 Single Enrichment Core with Dummy Rods | Hoon Song, Young In Kim,and Yeong Il Kim (KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | Analysis of Heat Transfer Characteristic in Upper Part of KALIMER-600 Reactor Vessel | Tae-Ho Lee, Rae-YoungPark, Seung-Hwan Seong, Jae-Hyuk Eoh, and Seong-OKim (KAERI) | PDF보기 | - | ||
| 2007-Spring | 제1분과 원자로기술 | Analysis of the Nonlinear Parallel-Flow Two-Phase Instability in a Liquid Metal Reactor SteamGenerator | Seok-Ki Choi and Seong-OKim (KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
