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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2005-Autumn 제1분과 : 원자로기술 Evaluation of SDS1 Depth for Pressure Tube Ruputure in Wolsong-1 NPP Kim YunHo and Choi Hoon (KEPRI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 REFORM Optimization to Improve ROPT Margins for Wolsong-1 Park Dong Hwan (GNEST) Lee Eun Ki, Kim Yun Ho, and Kim Yong Bae (KEPRI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Velocity of Delayed Hydride Cracking with Stress Intensity Factor in Zr-2.5Nb Pressure Tube Kang Soo Kim, Young Suk Kim, Yong Moo Cheong, Sang Bok Ahn, and Kyoung Soo Im (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 A Conceptual Core Design of a High Temperature Reactor Cooled by Super Critical Water Kang-Mok Bae, Hyung-Kook Joo, Hyun-Chul Lee, Jae-Man-Noh, and Yoon-Yong Bae (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Single Phase Turbulent Mixing in Square Rod Arrays at Highly Turbulent Condition Hae-yong Jeong, Kwi-seok Ha, Young-min Kwon, Sun Heo, Won-pyo Chang, and Yong-bum Lee (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Development of a Multidimensional Analysis Methodology for a Sodium-water Reaction in a SFR Steam Generator Seyun Kim, Jae-Hyuk Eoh, Won-Dae Jeon, and Seong-O Kim (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Structural Integrity Evaluation of the KALIMER-600 Reactor Core Support Structure Chang-Gyu Park, Jong-Bum Kim, and Jae-Han Lee (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Mechanical Design Features of the KALIMER-600 Sodium-cooled Reactor Jae-Han LEE, Chang-Gyu Park, and Jong-Bum Kim (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Under-sodium Inspection Techniques for Reactor Internals of KALIMER-600 Using Ultrasonic Waveguide Sensor Young-Sang Joo, Seok-Hoon Kim, and Jae-Han Lee (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 A Preliminary Evaluation of the Shutdown Margin of KALIMER-600 Jin-wook Jang and Yeong-il Kim (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Hydrogen Production Costs of Various Primary Energy Sources Jae-Hyuk Choi, Nam-il Tak, Yonghee Kim, and Won Seok Park(KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 The Temperature Dependent Inelastic Material Characteristics of Cold Worked 316L for NONSTA Jong-Bum Kim, Hyeong- Yeon Lee, Chang-Gyu Park, Se-Hwan Lee, and Jae-Han Lee (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Prediction of Void Fraction in Subcooled Boiling Kwi-Seok Ha, Hae-Young Jeong, Young-Min Kwon, Won-Pyo Chang, Eui-Kwang Kim, and Yong-Bum Lee (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Performance Test for Developing the Acoustic Leak Detection System of the LMR Steam Generator Tae-Joon Kim, Ji-Young Jeong, and Seop Hur (KAERI) PDF보기 -
2005-Autumn 제1분과 : 원자로기술 Evaluation of Tube Rupture Propagation in a SFR Steam Generator During a SWR Event Jae-Hyuk Eoh, Seyun Kim, Won-Dae Jeon, and Seong-O Kim (KAERI) PDF보기 -
Last Modified : 1998-Autumn