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) | 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 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Multi-dimensional Aspects of the 50% DVI Line Break Test with the ATLAS Facility | Ki-Yong Choi, Seok Cho, Hyun-Sik Park, Kyoung-Ho Kang, Nam-Hyun Choi, Yeon-Sik Kim, and Won-Pil Baek | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Counter-part Test Results of the LSTF SB-CL-18 Using the ATLAS | Seok Cho, Ki-Yong Choi, Hyun-Sik Park, Kyoung-Ho Kang, Yeon-Sik Kim, Nam-Hyun Choi, and Won-Pil Baek | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Effect of Break Location during ATLAS SBLOCA Tests for APR1400 | Hyun-Sik Park, Seok Cho, Ki-Yong Choi, Nam-Hyun Choi, Yeon-Sik Kim, and Won-Pil Baek(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Thermal-hydraulic Integral Effect Test Result on the Steam Generator Tube Rupture Accident in the APR1400 | Kyoung-Ho Kang, Seok Cho, Hyun-Sik Park, Nam-Hyun Choi, In-Cheol Chu, Byong-Jo Yun, Kyung-Doo Kim, Y | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Prediction of Major Transient Scenarios for Severe Accidents of Nuclear Power Plants Using GMDH | Young Gyu No, Sung Han Lee, Yung Hwa Shin, and Man Gyun Na(CSU) | PDF보기 | - |
Last Modified : 1998-Autumn
