-->

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2017-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Fabrication and Out-of-pile Test of Large grain UO2 pellets JangSoo Oh(KAERI), KeonSik Kim(KAERI), Dong-Soo Kim(KAERI), JongHun Kim(KAERI), DongSeok Kim(KAERI), and JaeHo Yang(KAERI) PDF보기 -
2017-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Characterization of Additive-Doped UO2 Pellets with Thermal Annealing Tests Dong Seok Kim(KAERI), Jang Soo Oh(KAERI), Dong-Joo Kim(KAERI), Jong Hun Kim(KAERI), Keon Sik Kim(KAERI), and Jae Ho Yang(KAERI) PDF보기 -
2017-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) The effects of Cr2+ ion irradiation on the formation of precipitation in multi-metallic layer composite cladding processed by hot isostatic pressing Tae Yong Kim(UNIST), Jeong Hyeon Lee(UNIST), and Ji Hyun Kim(UNIST) PDF보기 -
2017-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Preliminary Conceptual Design for U-Zr Fuel Manufacturing Facility Jong-Hwan Kim(KAERI), Ki-Hwan Kim(KAERI), SeongWoo Kuk(KAERI), Jung Won Lee(KAERI), Seok-Jin Jin(KAERI), Young-Ho Lee(KAERI), Jeong-Yong Park(KAERI), and , Chan Bock Lee(KAERI) PDF보기 -
2017-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Oxidation Behavior of Zirconium Alloys with Nanostructured Oxide Films in High Temperature Steam Environments Yang Jeong Park(KAIST), Jung Woo Kim(KAIST), and Sung Oh Cho(KAIST) PDF보기 PPT보기
2017-Spring 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) High Temperature Oxidation Behavior of the Aluminide Coated Refractory Samples in Steam Environment Je-Kyun Baek(KAIST), Woojin Lim(KAIST), JaeJoon Kim(KAIST), and Ho Jin Ryu(KAIST) PDF보기 -
2017-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Varification of Magnetostrictive Guided Wave Technique with an Elimination of Unwanted Geometry Signals for Detection and Monitoring of Defects in a Pipe Weld Yong-Moo Cheong(KAERI), Se-Beom Oh(KAERI), Duck-Hyun Lee(KAERI), and Kyung-Mo Kim(KAERI) PDF보기 -
2017-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Estimation of primary radiation damage cross sections for iron Junhyun Kwon(KAERI), Gyeong-Geun Lee(KAERI), Kunok Chang(KAERI), Hyung-Ha Jin(KAERI), and Sangyeob Lee(KAERI) PDF보기 -
2017-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) FAC test on the dissimilar metal welded pipeline in high flow conditions Kyung Mo Kim(KAERI), Jong Yeon Lee(KAERI), Eun Hee Lee(KAERI), Yong-Moo Choeng(KAERI), Se-Beom Oh(KAERI), and Dong-Jin Kim(KAERI) PDF보기 -
2017-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Development of Material Databases and Volume Heat Source for Temper Bead Welding Process Jangho Ahn(ESI Korea), Won Geun Yi(DOOSAN), and Sungbu Choi(KINS) PDF보기 -
2017-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Sensitization Condition of Alloy 182 Welds Joined by Stainless Steel 304 and Low Alloy Steel SA 508 Jae Young Yoon(KAERI), Tae Hyun Lee(KIMM), and Il Soon Hwang(SNU) PDF보기 -
2017-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Eddy Current Simulation for?Steam Generator Tube with Deposit Ga-Hyun Choi(KAERI), Duck-Hyun Lee(KAERI), and Kyung-Mo Kim(KAERI) PDF보기 -
2017-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Development of High Temperature Oxidation Resistant High Entropy Alloys for Coating Materials of Accident Tolerance Fuel Cladding JaeJoon Kim(KAIST) and HoJin Ryu(KAIST) PDF보기 -
2017-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Radiation Hardening and Swelling in Ti-bearing Reduced Activation Ferritic-Martensitic Steels Jungwoo Huh(MJU), Chansun Shin(MJU), Hyung-Ha Jin(KAERI), and Chang-Hoon Lee(KIMS) PDF보기 -
2017-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 로비 (3F) Effect of Copper Addition on Oxide Properties and Corrosion Resistance of Niobium Containing Zirconium Alloy in High Dissolved Hydrogen Primary Water Chemistry Yunju Lee(UNIST), Taeho Kim(UNIST), and Ji Hyun Kim(UNIST) PDF보기 -
Last Modified : 1998-Autumn