-->

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) Texture and Microstructure Development of Zr Alloy during Cold-rolling Yan Zhang LIU, Hyun Gil KIM, Byung Kwan CHOI, Jeong Yong PARK, and Yong Hwan JEONG (KAERI) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) Non-contact Thickness Measurement of a Nonmagnetic Plate Using EMAT H. K. Jung, K. C. Huh, and Y. M. Cheong (KAERI) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) Corrosion and Creep Characteristics of the HANA-4 Alloy with the Various Manufacturing Processes Hyun-Gil Kim, Byung- Kwan Choi, Jeong-Yong Park, and Yong-Hwan Jeong (KAERI) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) An in Situ Dispersoid Formation in ODS Steels by a Wet Processing Ho Jin Ryu, Min Ho Kim, Chang Hee Han, and Jinsung Jang (KAERI) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) VHTR Materials R&D in KAERI Ji Yeon Park, Dong Jin Kim, Dae Whan Kim, Sung Ho Kim, Woo Gon Kim, Weon-Ju Kim, Eung Sun Kim, and H PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) Model-based Approach for Long-term Creep Curves of Alloy 617 for a High Temperature Gas-cooled Reactor Woo Gon Kim, Song Nan Yin, and Yong Wan Kim (KAERI) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) High Temperature Degradation Behavior and its Mechanical Properties of Inconel 617 Alloy for Intermediate Heat Exchanger of VHTR Tae Sun Jo, Se-Hoon Kim, and Young Do Kim (HYU) Ji Yeon Park (KAERI) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) Mechanical Properties of Candidate Materials for Hot Gas Duct of VHTR Dae Whan Kim and Yong Wan Kim (KAERI) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) Corrosion of Materials in Sulfuric Acid for Hydrogen Production by Using VHTR Dong-Jin Kim, Hyuk Chul Kwon, Hong Pyo Kim, and Yong Wan Kim (KAERI) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) Thermal Oxidation Behaviors of Candidate Nuclear Grade Graphites for VHTR at High Temperatures above 900oC Eung-Seon Kim and Yong-Wan Kim (KAERI) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) Oxidation and Temperature Effects on the Fracture Toughness of Nuclear Graphite at VHTR Byung Jun Kim, Daejong Kim, and Changheui Jang (KAIST) Se-Hwan Chi (KAERI) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) Stress Analysis of Surge Line due to Thermal Stratification Myung Jo Jhung and Young Hwan Choi (KINS) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) Development of a Prototypal Integrity Assessment Program for Flawed Tubes Jae-Uk Jeong, Seung-Cheon Yu, Yoon-Suk Chang, and Young-Jin Kim (SKKU) Seong-Sik Hwang and Hong-Pyo PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) The Effect of Residual Stress on the Stress Intensity Factor of Nuclear Material Taek-Ho Song (KEPRI) PDF보기 -
2008-Spring 제4분과 : 핵연료및원자력재료(Division of Nuclear Fuel and Materials) A Fuzzy Support Vector Regression Model for Estimation of Collapse Moment of Wall-Thinned Pipes In Ho Bae, Man Gyun Na, and Jin Weon Kim (CSU) PDF보기 -
Last Modified : 1998-Autumn