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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2007-Spring 제4분과 원자력재료 및 연료 Wear Progress and Mechanism of Alloy 600 SG Tube by Impact and Sliding Motion Chi-Yong Park, Jeong-Kun Lee, Tae-Ryong Kim(KEPRI) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Fatigue Properties of Aged Mod. 9Cr-1Mo Dae Whan Kim, Sung Ho Kim, Chan Bock Lee(KAERI) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Selection and Creep Property of Alloy 617 for the IHX Application Woo Gon Kim, Song Nan Yin, Chang Hee Han, Yong Wan Kim, Jong Hwa Chang(KAERI) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Development of Post-Irradiation Test Techniques for the Components of a Nuclear Fuel Assembly in a Hot Cell Dosik Kim, Yong-Sun Choo, Sang-Bok Ahn, Byung-Ok Yoo, Seung-Je Baik, Ki-Ha Kim, Woo-Seog Ryu(KAERI), PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Study on the Performance of Inhibitors for a SCC of SG Tube Materials Kyung Mo Kim, Eun Hee Lee, Uh Chul Kim and Wan Young Maeng(KAERI) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Motion of Defect Clusters and Dislocations at a Crack Tip of Irradiated Material Won-Jin Moon(KBSI), Sang Chul Kwon, Whung Whoe Kim(KAERI) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Reduction of Conservativeness in Thermal Stratification Analysis for LBB Application Byongsup Kim, Youngho Jang(KHNP) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Environmental Effect on the Characteristics of the Low Cycle Fatigue of SA508 Gr.1a Low Alloy Steel Byongsup Kim, Cheolhwan Oh, Taesoon Kim(KHNP), Hyunchul Cho(KAIST) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Stress Distribution in the Direction of 1-D Motion of an Interstitial Loop Sang Chul Kwon, Whung Whoe Kim(KAERI), Won-Jin Moon, Young-Min Kim(KBSI) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 A Preliminary Study on a Piping-FAC Mitigation in a Deoxygenated Solution at pH 8.5 and 150℃ by a Platinum Dioxide Doping Ki Woung Sung, Hyun Il Seo, Eun Hee Lee, Uh Chul Kim, Wan Young Maeng(KAERI) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Analysis of Neutron Absorbing Impurities in Nuclear Graphite Joon Hee Jang, Se-Hwan Chi(KAERI) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Effect of Hydrogen on the Creep of Zircaloy-4 Cladding Tubes Tae Wook Oh, Young Suk Kim, Sang Bok Ahn, Kyung Soo Im, Yong Moo Cheong(KAERI) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Analysis on Axial Cracks of Steam Generator Tubes Using Multi-Parameter Algorithm Ch. Nam-Gung, Y.M. Cheong, H.P. Kim, S.S. Hwang(KAERI) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Technique Comparison of the Fracture Toughness Tests for Irradiated Fuel Claddings in a Hot Cell Sangbok, Ahn, Dosik KIM, Yanghong Jung, Yongsun Choo, Wooseog Ryu(KAERI) PDF보기 -
2007-Spring 제4분과 원자력재료 및 연료 Long-term Creep Life Prediction for Type 316LN Stainless Steel Woo Gon Kim, Woo Seog Ryu, Sung Ho Kim, Chan Bok Lee(KAERI) PDF보기 -
Last Modified : 1998-Autumn