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) | Development of a Fabrication Process for a High Strength FM Steel | Tae Kyu Kim, Chang Hee Han, Sung Ho Kim, and Chan Bock Lee(KAERI) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | New Methodology to Predict the Long-term Creep Strength of Alloy 617 for a Very High Temperature Reactor | Woo Gon Kim, Song Nan Yin, Gyeong-Geon Lee, and Yong Wan Kim(KAERI) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | Development of the PARA-ID Program to Simulate a Unified Viscoplasticity Behaviour | Gyeong-Hoi Koo(KAERI) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | Comparison of ASME Code NB-3200 and NB-3600 Results for Fatigue Analysis of Primary Piping Spray Nozzle | H. S. Lee, S. B.Han, and K. H. Lee(GNEC), J. G. Lee(KHNP) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | LBB Assessment of Pressurizer Surgeline Using NUREG-CR/6765 Level 3 Approach | Y.H.Jang, B.H.Bae, and T.S.Kim(KHNP) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | Mesh Size Effects on Fracture Toughness Estimation by Damage Model | Shin-Beom Choi, Yoon-Suk Chang, and Young-Jin Kim(SKKU) Min-Chul Kim and Bong-Sang Lee(KAERI) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | Collapse Moment Prediction for the Wall-thinned Pipe Bends Using Fuzzy Neural Networks and Uncertainty Analysis | Sung Han Lee, Dong Hyuk Lim, and Man Gyun Na(CSU) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | Aging Effect on Corrosion and Microstructure of Zr- 1.5Nb-0.4Sn-0.2Fe-0.1Cr Alloy | Hyun-Gil Kim, Byung-Kwan Choi, Sang-Yoon Park, Myung-Ho Lee, Jeong-Yong Park, and Yong-Hwan Jeong(KA | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | Effect of Silicon on the Microstructures and Tensile Properties of Austenitic ODS Stainless Steels for Fast Reactor Cladding | Min Ho Kim, Ho Jin Ryu, Chang Hee Han, Sung Soo Kim, and Jinsung Jang(KAERI) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | Effect of Vanadium on the Creep Properties of SFR Fuel Cladding Tube Materials | Sung-Ho Kim, Chan bock Lee, and Dohee Hahn(KAERI) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | Effect of a Hot Rolling Process on the Mechanical Behavior of 9Cr-1Mo Steel | Jun Hwan Kim, Chang Hee Han, Sung Ho Kim, and Chan Bock Lee(KAERI) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | Effects of Boron Addition on Creep and Microstructure in 9Cr-0.5Mo-2W-V-Nb-B Steels for a SFR Fuel Cladding | Jong-Hyuk Baek, C. -H. Han, W. -G. Kim, T. -K. Kim, J. -H. Kim, S. -H. Kim, and C. -B. Lee(KAERI) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | Thermo-mechanical Behavior of a H4 Outer Strip in the Transverse Direction | Myung Ho Lee, Yang Il Jung, Sang Yoon Park, Byoung Kwon Choi, Jeong Yong Park, Hyun Gil Kim, and Yon | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | Study on the Segregation Behavior in SA508 Gr. 4N Low Alloy Steel with Mn Contents Variation | Sang Gyu Park and Dang Moon Wee (KAIST) Min-Chul Kim and Bong Sang Lee (KAERI) | PDF보기 | - | ||
| 2009-Spring | 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) | A Study on the Thermal Stability of Electrodeposited Ni-P-Fe and Ni-P-B at 325℃ | Myong Jin Kim, Sang-Hyun Ryu, Dong Jin Kim, Joung Soo Kim, and Hong Pyo Kim(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
