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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2020-Spring 1A : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Characteristics of Braided Wire Wick Heat Pipe for Heat Pipe Cooled Reactor Byung Ha Park and Chan Soo Kim(KAERI) PDF보기 -
2020-Spring 1A : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Study of Diameter Variation Affecting the Thermal Performance of Heat Pipe for Space Nuclear Reactor Applications Ye Yeong Park and In Cheol Bang(UNIST) PDF보기 -
2020-Spring 1A : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Experiment Status of Supercritical CO2 Turbo Alternator Compressor (TAC) Supported with Ceramic Ball Bearing Seong Kuk Cho, Seongmin Son, Yongju Jeong and Jeong Ik Lee(KAIST) PDF보기 -
2020-Spring 1B : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Preliminary Thermodynamic Analysis of LAES Integrated Nuclear Power Plant Junghwan Park, Seunghwan Oh, Youngjae Choi, Jinyoung Heo and Jeongik Lee(KAIST) PDF보기 -
2020-Spring 1B : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Effect of Short Range Ordering on Lattice Variation in Garter Spring (X-750) in CANDU Sung Soo Kim and Jong Yup Jung(KAERI), Young Suk Kim(MacTec) PDF보기 -
2020-Spring 1B : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Diameter Evaluation Methodology for Un-measured Pressure Tubes of CANDU Reactor Jong Yeob Jung and Eun Hyun Ryu(KAERI) PDF보기 -
2020-Spring 1B : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line FACAPT - Failure Assessment Program for CANDU Pressure Tube Jong Yeob Jung(KAERI), Ji Hoon Kang(FNC Tech.), Yoon Suk Chang(KHU) PDF보기 -
2020-Spring 1B : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Preliminary Analysis about SBO-induced Severe Accident at CANDU-6 using M-CAISER Code Jun-young Kang, Dong Gun Son, Yong Mann Song, Sang Ho Kim, Ki Hyun Kim, Jong Yeob Jung and Jun Ho Bae(KAERI), Jae Ho Bae and Jae Seung Suh(SENTECH) PDF보기 -
2020-Spring 1B : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Preliminary Evaluation of Small LOCA under Severe Accident Conditions Using ISAAC and M-CAISER in Wolsong Plants Y.M. Song, J.Y. Jung, J.Y. Kang, D.G. Son and J.H. Bae(KAERI), Jae Ho Bae(SENTECH) PDF보기 -
2020-Spring 1B : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Estimation of Gain Factors for the Cold Neutron Source in European Research Reactor Han Jong YOO, Kyung-O KIM, Byungchul LEE and Gyuhong ROH(KAERI) PDF보기 -
2020-Spring 1B : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Application of Computational Fluid Dynamics for Generation of Hydraulic Forcing Functions on Reactor Internals Dong Hwa Jeong, Kyong In Ju and Seong Chan Park(KEPCO E&C) PDF보기 -
2020-Spring 1C : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Transient Analyses of the S-CO2 Cycle Coupled to PWR for Nuclear Marine Propulsion Jeong Yeol Baek, Jae Jun Lee and Jeong Ik Lee(KAIST) PDF보기 -
2020-Spring 1C : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line SBLOCA Analysis of SMART with Trans-Critical CO2 Power Conversion System for Maritime Propulsion Bong Seong Oh and Jeong Ik Lee(KAIST) PDF보기 -
2020-Spring 1C : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Preliminary Analysis of Passive Residual Heat Removal System for a Nuclear-powered Ship Wooseong Park and Yong Hoon Jeong(KAIST) PDF보기 -
2020-Spring 1C : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Preliminary Safety Analysis of Design Basis Events for TRU Burner Reactor Jae-Ho Jeong(Gachon Univ.), Jonggan Hong(KAERI) PDF보기 -
Last Modified : 1998-Autumn