학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | CFD Validation with a Multi-Block Experiment to Evaluate the Core Bypass Flow in VHTR | Su-Jong Yoon, Jeong-Hun Lee, and Goon-Cherl Park(SNU) Min-Hwan Kim(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | Thermal Stress Assessment of Graphite Fuel Blocks in a Very High Temperature Reactor Core | Ji-Ho Kang, Nam-il Tak, and Min-Hwan Kim(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | Overpressure Predictions by the MEM and the Baker-strehlow-Tang Blast Curves for the SRI H Explosion Test in the Open Space | H.S.Kang, S.B.Kim, and M.H.Kim(KAERI) H.C.No(KAIST) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | An Analysis of the Secondary Cooling System Repair Status after the Initial Operation of HANARO | Young-Chul Park(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | Introduction of Measuring Instruments Used at Sodium Thermal Hydraulic Test Facilities in KAERI | Tae-Joon Kim, Tae-Ho Lee, In-Koo Hwang, Ji-Young Jeong, Jong-Hyeun Choi, Jong-Man Kim, Byoung-Hae Ch | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | Analysis of Local Recirculation Flow under Sub-channel Blockage Accident | Won-Pyo Chang, Young-Min Kwon, Ki-Suk Ha, and Hae-Yong Jeong(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | Effect of Molten Steel on CDA Energetics | S.D.Suk and H.Y.Jeong(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | Long-term Cooling Capability of KALIMER-600 PDRC | Kwi-Seok Ha, Young-Min Kwon, Won-Pyo Chang, Kwi-Lim Lee, and Hae-Young Jeong(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | An Automatic Approach to the Stabilization Condition in a HIx Distillation Simulation | Jiwoon Chang, Youngjoon Shin, Kiyoung Lee, Yongwan Kim, and Jonghwa Chang(KAERI) Cheung Youn(CNU) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | A Scoping Analysis of the Performance Test Loop of PDRC with the MARS-LMR Code | Kwi Lim Lee, Kwi Suk Ha, and Hae-Yong Jeong(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | Passive Safety Characteristics of the 1200MWe GEN-IV Sodium-Cooled Fast Reactor | Young-Min KWON, Kwi-Lim LEE, Kwi-Seok HA, Hae-Yong JEONG, and Won-Pyo CHANG(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | Development of a Water Scaled Model for the Thermal Hydraulic Study of 600MWeSFR | J.E.Cha, S.H.Lee, S.O.Kim, and Y.I.Kim(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | Power Control Logic Evaluation of RRS for SMART | Yu-Lim Jeon, Han-Ok Kang, Seong-Wook Lee, and Cheon-Tae Park(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | Core Thermal-Hydraulic Conceptual Design for the Advanced SFR Design Concepts | Chungho Cho, Jinwook Chang, Jae-Woon Yoo, Hoon Song, Sun-Rock Choi, Won-Seok Park, and Sang-Ji Kim(K | PDF보기 | - | ||
| 2010-Spring | 제1분과 : 원자로시스템기술(Nuclear Reactor System Technology) | Investigation of a Wastage Effect by a Potential CO Ingress in a Supercritical CO Power Conversion System of an SFR | Jae Hyuk EOH, Ji-Young JEONG, Jong-Man KIM, and Seong-O KIM(KAERI) Hee Cheon NO(KAIST) | PDF보기 | - |
Last Modified : 1998-Autumn
