학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | A Modeling on Gas Pressure Buildup within a Coated Fuel Particle | Kim Young Min, Y. K. Kim, S. C. Oh, K. C. Jeong, W. K. Kim, Y. W. Lee, and M. S. Cho(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Hydrogen Effects on Creep Behaviors of Zr Alloy Nuclear Fuel Cladding under Dry Storage Condition | Sun-Ki Kim, Je-Geon Bang, Dae-Ho Kim, Ik-Sung Lim, Yong-Sik Yang, and Yang-Hyun Koo(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Conceptual Design of Shielded Experimental Table for Thermal Conductivity Tester | Kwonpyo Hong, Dae-Gyu Park, Sang-Bok Ahn, and Woo-Seog Ryu(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | An Experiment on Specific Surface Area for Sintered Uranium Oxide with Additives of Nd O and CeO | C. J. Park, C. H. Kim, S. H. Na, J. H. Yang, K. H. Kang, and J. W. Lee(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | A High Temperature Neutron Study on Aged Alloy 690 | Sungsoo Kim(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Subsurface Deformation Behaviors of a Nuclear Fuel Rod under Elastically Deformable Contacts | Young-Ho Lee and Hyung-Kyu Kim(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Low Temperature and Rapid Sintering of UO Fuel Pellet by Induction Heating | Jae Ho Yang, Jong Hun Kim, Dong-Joo Kim, Ki Woo Kang, Young Woo Rhee, Keon Sik Kim, and Kun Woo Song | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Spherical UO2 Size and Microstructure on Broth Preparation Conditions | Jeong Kyung Chai, Kim Yeon Ku, Oh Seung Chul, Kim Woong Ki, Kim Young Min, Lee Young Woo, and Cho Mo | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Minimum Required Spring Force and In-grid Spring Analysis of Spacer Grids for DualCooled Fuels | JaeYong Kim, YoungHo Lee, KyungHo Yoon, and HyungKyu Kim(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Basic Design of Structural Components of a Dual Cooled Fuel for OPR-1000 | Hyung-Kyu Kim, Jae-Yong Kim, Kyung-Ho Yoon, Young-Ho Lee, Kang-Hee Lee, Heung-Seok Kang, and KunWoo | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Development of an End-plug Welding Technology for an Instrumented Fuel Irradiation Test | Soo-Sung Kim, Chul-Yong Lee, Yoon-Taek Shin, and Kee-Nam Choo(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Thermal Stress Analysis for the Plate Type Fuel Assembly | Kang Soo Kim, Jeong Soo Ryu, Jin Ho Oh, Jong Min Lee, and Chung Young Lee(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Unloading Effect on Delayed Hydride Cracking in Zirconium Alloys | Young Suk Kim and Sung Soo Kim(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Evaluation of a Ductility after High Temperature Oxidation with the Three-Point Bend Test in Zirconium Alloys | Yang-Il Jung, Sang-Yoon Park, Jeong-Yong Park, and Yong-Hwan Jeong(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 4 분과 : 핵연료 및 원자력 재료(Nuclear Fuel and Materials) | Creep Analysis of Zr-1.1Nb-0.05Cu Alloy Using Stress Relaxation Data | Yong-Nam Seol, Yang-Il Jung, Byoung-Kwon Choi, Jeong-Yong Park, and Yong-Hwan Jeong(KAERI) Sun-Ig Ho | PDF보기 | - |
Last Modified : 1998-Autumn
