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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Effects of Filler Size on Radiation Shields Jaewoo Kim, Byung Chul Lee, Young Rang Uhm, Jinwoo Jung, and Chang-Kyu Rhee(KAERI) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Diametral Compressive Strength and Elastic Modulus of Flattened Disc Using Diametral Compressive Test Donghoon Kim, Byung Jun Kim, and Changheui Jang(KAIST) Se-Hwan Chi(KAERI) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Fatigue Analysis of Tubesheet/Shell Juncture Applying the Mitigation Factor for Over-conservatism Deog Ji Kang, Kyu Hyoung Kim, and Jae Gon Lee(KHNP) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) The Effect of Inspection Model on the Probability of Vessel Failure due to Pressurized Thermal Shock Myung Jo Jhung and Young Hwan Choi(KINS), Changheui Jang(KAIST) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Development of an Integrated Multi-channel Ultrasonic System for Online Structural Health Monitoring of Large Structures Heung-Seop Eom and Jin-Ho Park(KAERI) Hak-Joon Kim and Sung-Jin Song(SKKU) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Flow-induced Vibration Measurement of an Inner Cladding Tube in a Simulated Dual-cooled Fuel Rod Kang-Hee Lee, Hung-Kyu Kim, Kyung-Ho Yoon, Young-Ho Lee, and Jae-Yong Kim(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Experimental Study on the Friction Loss Coefficient in a Micro Gap Ho-Yun Nam, Byoung-Hae Choi, Jong-Man Kim, and Byung-Ho Kim(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) CHF Enhancement of a Forced Convective Flow Boiling in Nanofluid HoSeon Ahn, HangJin Jo, SoonHo Kang, and MooHwan Kim(POSTECH) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Application of Zeta Potential Method for the Selection of Nano-fluids to Enhance IVR Capability Pham Quynh Trang, Tae Il Kim, and Soon Heung Chang(KAIST) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Analysis of Mixing Tests in an Annular Vessel C. K. Park, Y. J. Youn, H. G. Jun, and C. H. Song(KAERI) K. K. Lee and H. J. Ko(KOPEC) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simultaneous Measurements of Size and Velocity of Bubbles in an Opaque Tube Using X-ray PTV Technique Seok Kim and Chul Hwa Song(KAERI), Sang Joon Lee(POSTECH) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Steam Binding and Inhomogeneous Top Quenching Observed during ATLAS LBLOCA Reflood Tests Hyun-Sik Park, Seok Cho, Kyoung-Ho Kang, Ki-Yong Choi, Yeon-Sik Kim, and Won-Pil Baek(KAERI), Dae-Hu PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Nucleate Boiling Heat Transfer by the Hydrophobic Milli-dot on the Silicon Surface HangJin Jo, Ho Seon Ahn, Seontae Kim, Soon Ho Kang, Moo Hwan Kim, Hyungmo Kim, and Joonwon Kim(POSTE PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Measurements of Bubbly Flow in a Subchannel by Using Optical Sensor Probe Seok-Kyu Chang, Yeon-Jun Choo, Bok-Deuk Kim, In-Cheol Chu, Dong-Jin Euh, Won-Man Park, Byong-Jo Yun, PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) CHF Enhancement in Flow Boiling at Low Mass Flux Using Al2O3 Nano-fluid Tae Il Kim, Yong Hoon Jeong, and Soon Heung Chang(KAIST) PDF보기 -
Last Modified : 1998-Autumn