학술정보출판물

한국원자력학회에 오신 것을 환영합니다.

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2020-Spring 0A : 개회식 (Opening) 7.9(Thu)~7.10(Fri) On-line 종합일정 PDF보기 -
2020-Spring 0B : 개회식 및 주요행사 (Opening and Events) 7.9(Thu)~7.10(Fri) On-line (특별강연1) 코로나19 사태 장기화와 사회적 건강 Myoungsoon You PDF보기 -
2020-Spring 0B : 개회식 및 주요행사 (Opening and Events) 7.9(Thu)~7.10(Fri) On-line (특별강연2) 불확실성 시대의 ‘리스크 커뮤니케이션’ 그리고 원전 Yoo, Seung-Chul PDF보기 -
2020-Spring 1A : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line The Effect of Turbomachinery Performance Degradation on the Load-following Performance of S-CO2 Direct-cycle Micro Modular Reactor (KAIST-MMR) Seongmin Son and Jeong Ik Lee(KAIST) PDF보기 -
2020-Spring 1A : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Gap Assessment on the Moderator Temperature Distribution in a Space Reactor Sung Nam Lee, Nam-il Tak and Sung Hoon Choi(KAERI) PDF보기 -
2020-Spring 1A : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Design of an Experimental Apparatus to Test the Alkali-Metal Heat Pipes for Space Fission Power Sung Deok Hong and Chan Soo Kim(KAERI) PDF보기 -
2020-Spring 1A : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Changes of Mechanical Properties after 3-Years Thermal Ageing at 900°C of Alloy 617 Woo-Gon Kim, Injin Sah, Eung-Seon Kim, and Min-Hwan Kim(KAERI), I.N.C. Kusuma and Seon-Jin Kim(PKNU) PDF보기 -
2020-Spring 1A : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Turbulence Model Assessment for a Heated Rectangular Riser of Air-cooled RCCS in Turbulent Forced and Mixed Convection Heat Transfer Sin-Yeob Kim and Hyoung Kyu Cho(SNU), Chan-Soo Kim(KAERI) PDF보기 -
2020-Spring 1A : 원자로시스템기술 (Reactor System Technology) 7.9(Thu)~7.10(Fri) On-line Preliminary Thermal Analysis of Heat Pipe Cooled Reactor Core using Stress Analysis Solver in OpenFOAM Myung Jin Jeong, San Lee and Hyoung Kyu Cho(SNU) PDF보기 -
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 -
Last Modified : 1998-Autumn