학술발표회 논문집
Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
---|---|---|---|---|---|---|---|
2010-Autumn | 제4분과 : 핵연료 및 원자력 재료(Nuclear Fuel & Materials) - 핵연료 및 피복관(Fuel & Cladding) | Characterization of Pore Structure of Nuclear Grade Graphite Using Image Analysis Technique and Mercury Porosimetry | Eung-Seon Kim, Ji-seon song, and Sung-Deok Hong(KAERI) | PDF보기 | - | ||
2010-Autumn | 제4분과 : 핵연료 및 원자력 재료(Nuclear Fuel & Materials) - 핵연료 및 피복관(Fuel & Cladding) | Measurement of PWSCC CGR vs. K in the CRDM Alloy 60 | Yun Soo Lim, Hong Pyo Kim, and Han Hee Lee(KAERI) | PDF보기 | - | ||
2010-Autumn | 제4분과 : 핵연료 및 원자력 재료(Nuclear Fuel & Materials) - 핵연료 및 피복관(Fuel & Cladding) | Role of Grain Boundary Carbides in PWSCC Behavior of Ni Base Alloys | Seong Sik Hwang, Hong Pyo Kim, Yun Soo Lim, and Sung Woo Kim(KAERI) | PDF보기 | - | ||
2010-Autumn | 제4분과 : 핵연료 및 원자력 재료(Nuclear Fuel & Materials) - 핵연료 및 피복관(Fuel & Cladding) | The Investigation of the Effects of the Chloride Ion Concentration and the Crevice Geometry on the Denting Corrosion | Myong-jin Kim, Dong Jin Kim, Joung Soo Kim, and Hong Pyo Kim(KAERI) | PDF보기 | - | ||
2010-Autumn | 제4분과 : 핵연료 및 원자력 재료(Nuclear Fuel & Materials) - 핵연료 및 피복관(Fuel & Cladding) | A Study on Corrosion Behaviors of SS 316L in Liquid Gallium Environments | Sang Hun Shin, Jong Jin Kim, Jeong Seok Park, In Cheol Bang, and Ji Hyun Kim(UNIST) | PDF보기 | - | ||
2010-Autumn | 제4분과 : 핵연료 및 원자력 재료(Nuclear Fuel & Materials) - 핵연료 및 피복관(Fuel & Cladding) | Thermodynamic Study on the Surface of Nickel-base Alloys in Hydrogenated Water | Hyo On Nam and Il Soon Hwang(SNU) Kyu Hwan Lee(KIST) | PDF보기 | - | ||
2010-Autumn | 제4분과 : 핵연료 및 원자력 재료(Nuclear Fuel & Materials) - 핵연료 및 피복관(Fuel & Cladding) | Through-thickness Measurements of Residual Stresses in an Overlay Dissimilar Weld Pipe Using Neutron Diffraction | Wanchuck Woo, Vyacheslav EM, Ho-Jin Lee, Kang Soo Kim, Mi-Hyun Kang, Jongdae Joo, and Baek-Seok Seon | PDF보기 | - | ||
2010-Autumn | 제4분과 : 핵연료 및 원자력 재료(Nuclear Fuel & Materials) - 핵연료 및 피복관(Fuel & Cladding) | Fatigue Crack Growth Rate of Type 347 Stainless Steel at the PWR Environment | Ki-Deuk Min and Seon-Jin Kim(HYU) Dae-Whan Kim and Bong-Sang Lee(KAERI) | PDF보기 | - | ||
2010-Autumn | 제4분과 : 핵연료 및 원자력 재료(Nuclear Fuel & Materials) - 핵연료 및 피복관(Fuel & Cladding) | Effects of Specimen Size on the Flexural Strength and Weibull Modulus of Nuclear Graphite | Se-Hwan Chi, Dae-In Kim, Eung-Seon Kim, Sung-Deok Hong, and Yong-Wan Kim(KAERI) | PDF보기 | - | ||
2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Extremely High Leidenfrost Temperature on Nanoparticle-deposited Surfaces and Its Influences on Quenching Phenomena | Hyungdae Kim(KHU) | PDF보기 | - | ||
2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Design of the Test Rig for Experimental Study on Flow Dynamics of Air-water Bubbly Flow in a Bundle Array | Seok-Kyu Chang and Chul-Hwa Song(KAERI) | PDF보기 | - | ||
2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Experimental Validation of Bubble Departure and Lift-off Diameter Models under the Low Heat Flux and Low Flow Velocity Conditions | Yun-Je Cho and Goon-Cherl Park(SNU) Heung-June Chung(KAERI) | PDF보기 | - | ||
2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Pool Boiling CHF Enhancement on Modified Zirconium Alloy | Ho Seon Ahn, Hang Jin Jo, Soon Ho Kang, and Moo Hwan Kim(POSTECH) | PDF보기 | - | ||
2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Experimental Investigation on the CHF Enhancement of Pool Boiling Using Magnetic Fluid | Jong Hyuk Lee and Yong Hoon Jeong(KAIST) | PDF보기 | - | ||
2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Effects of Magnetic Field on Flow Boiling CHF in Fe3O4 Ferrofluid | Taeseung Lee, Hae Min Park, Jong Hyuk Lee, and Yong Hoon Jeong(KAIST) | PDF보기 | - |
Last Modified : 1998-Autumn