-->

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) Fitting UO2 Interatomic Potential Using Micro-genetic Algorithm Jae-Yong Oh, Yang-Hyun Koo, and Byung-Ho Lee(KAERI) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Hot Spot Analysis around the Contact Zone between Fuel Rod and Spacer Grid Jin Seok Lee, Kwang Ho Yoon, Yong Hwan Kim, and Kyeong Lak Jeon(KNF), Won Dae Jeon(CD-adapco) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Improvement on the End Plug For an Instrumented Nuclear Fuel Rod for the Irradiation Test at HANARO Sungjae Park, Jaemin Sohn, Bonggoo Kim, Keenam Choo, and Youngki Kim(KAERI) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Measurement of the Thermal Diffusivity of UO2 with Sample Holders for PIE in a Hot-cell Heemoon Kim, Dae Gyu Park, Sang Ho Na, Chang Je Park, Kweon Ho Kang, Seung Jai Baik, and Sang-Bok Ah PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Phenomenological Modeling of Fission Gas Release in LWR UO2 Fuel under RIA Conditions Yang-Hyun Koo, Jae-Yong Oh, and Byung-Ho Lee(KAERI) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Proficiency Testing Schemes of a Fuel Assembly Performance Method by Comparing of Measurement Results of Two Tester K. H. Yoon, J. K. Kim, K. H. Lee, Y. H. Lee, and H. K. Kim(KAERI) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Standardless Quantitative Analysis of PWR Spent Fuel with WDS-SEM Hyoung-Mun Kwon, Yong-Sik Yang, June-Sik Ju, Wan-Ho Oh, Jung-Nam Jang, and Yong-Bum Chun(KAERI) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Trial Run of the Performance Test Facility for Fuel Assembly Hydraulics and Vibrations Analyses C. H. Shin, H. K. Kim, B. D. Kim, J. K. Park, S. Y. Chun, and D. S. Oh(KAERI) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Structural Integrity Evaluation of Fuel Assembly Bottom Nozzle for OPR 1000 Joon-Kyoo Park, Jin-Seok Lee, Jung-Min Suh, and Kyeong-Lak Jeon(KNF) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Design of the Flow Plates for a Dual Cooled Fuel Assembly Jae Yong Kim, KyungHo Yoon, YoungHo Lee, KangHee Lee, and Hyungkyu Kim(KAERI) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Environmental Fatigue Behaviors of Type 316LN Stainless Steels in Simulated PWR Water with Different Dissolved Hydrogen Contents - Preliminary Results Hun Jang, Pyung Yeon Jo, and Changheui Jang(KAIST) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) PWSCC in Alloy 600 and IG Crack Growth Rates in PWR Environments Y. C. Jung, H. S. Chung, K. S. Lee, and N. H. Heo(KEPRI) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) PWSCC Mechanism of Alloy 600 Hong Pyo Kim, Y. S. Lim, S. W. Kim, S. S. Hwang, D. J. Kim, S. S. Kim, J. S. Kim, J. Y. Park, and M. PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Causes of PWSCC in a Alloy 600 Nozzle of a PWR Seong Sik Hwang, Yun Soo Lim, Jangyul Park, and Hong Pyo Kim(KAERI) PDF보기 -
2009-Spring 제 4 분과 핵연료 및 원자력재료(Nuclear Fuel and Materials) Transmission Electron Microscopy Characterization of PWSCC Cracks in Alloy 600 Yun Soo Lim, Hong Pyo Kim, Hai Dong Cho, and Han Hee Lee(KAERI) PDF보기 -
Last Modified : 1998-Autumn