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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2016-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 11:20 203 (2F) A 2.5 MWT Passive Decay Heat Removal System Design for PGSFR Dehee Kim, Jaehyuk Eoh, and Tae-Ho Lee(KAERI) PDF보기 -
2016-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 11:40 203 (2F) 2-D FEM Simulation of Propagation and Radiation of Leaky Lamb Wave In a Plate-type Ultrasonic Waveguide Sensor Sang-Jin Park, Hoe-Woong Kim, Young-Sang Joo, Sung-Kyun Kim, and Jong-Bum Kim(KAERI) PDF보기 -
2016-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 12:00 203 (2F) FEA Stress Analysis Considering Cavity Formation of Metallic Fuel Pin under Transient State Hyun-Woo Jung, Young-Ryun Oh, and Yun-Jae Kim(KU) PDF보기 PPT보기
2016-Spring 1D : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 09:00 401B (4F) (초청발표1) Anisotropic Material Behavior of Uni-axially Compacted Graphite Matrix for HTGR Fuel Compact Fabrication Young-Woo Lee, Seunghwan Yeo, Ji-Hae Yoon, and Moon Sung Cho(KAERI) PDF보기 -
2016-Spring 1D : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 09:30 401B (4F) (초청발표2) VHTR-based Nuclear Hydrogen Plant Analysis for Hydrogen Production with SI, HyS, and HTSE Facilities Youngjoon Shin, Taehoon Lee, Kiyoung Lee, and Minhwan Kim(KAERI) PDF보기 -
2016-Spring 1D : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 10:00 401B (4F) A Research Status on High-Temperature Creep of Alloy 617 for Use in VHTR System Woo-Gon Kim, Jae-Young Park, Eung-Seon Kim, Yong-Wan Kim, and Min-Hwan Kim(KAERI), Seon-Jin Kim(PKNU) PDF보기 -
2016-Spring 1D : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 10:20 401B (4F) A Conceptual Study of Using an Isothermal Compressor on an S-CO2 Cooled KAIST Micro Modular Reactor (KAIST-MMR) Jin Young Heo, Yoonhan Ahn, and Jeong Ik Lee(KAIST) PDF보기 PPT보기
2016-Spring 1D : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 11:00 401B (4F) Characterization of Corrosion Behaviors of Candidate Materials in Sulfuric Acid Environment Injin Sah, Jae-Won Park, Eung-Seon Kim, and Min-Hwan Kim(KAERI) PDF보기 -
2016-Spring 1D : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 11:20 401B (4F) Cyclic Deformation and Fatigue Behaviors of Alloy 617 Base Metal and Weldments at 900℃ for VHTR Applications Seon-Jin Kim, Rando T. Dewa, Jeong Jun Hwang, Tan Su Kim, and Byung Tak Kim(PKNU), Woo-Gon Kim and Eung Seon Kim(KAERI) PDF보기 -
2016-Spring 1D : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 11:40 401B (4F) Effect of Permanent Side Reflector on the Temperature Variation in the VHTR Core Sung Nam Lee, Nam-il Tak, and Min-Hwan Kim(KAERI) PDF보기 -
2016-Spring 1D : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 12:00 401B (4F) Application of Looped Network Analysis Method to Core of Prismatic VHTR Jeong-Hun Lee, Hyoung-Kyu Cho, and Goon-Cherl Park(SNU) PDF보기 PPT보기
2016-Spring 1D : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 12:20 401B (4F) Calculation of Thermal-Fluid Parameters for the Pre-designed VHTR Core Based on CORONA Jun Kyu Song, Bong Hyun Cho, Nam-il Tak, and Chang Keun Jo(KAERI) PDF보기 -
2016-Spring 1E : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 14:00 203 (2F) (초청발표1) Mechanical Design Features of PGSFR NSSS Chang-Gyu PARK, Gyeong-Hoi KOO, Jae-Hun CHO, and Sung-Kyun KIM(KAERI) PDF보기 -
2016-Spring 1E : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 14:30 203 (2F) Creep-Fatigue Damage Evaluation of a Model Reactor Vessel and Reactor Internals of Sodium Test Facility According to ASME-NH and RCC-MRx Codes Dong-Won Lim, Hyeong-Yeon Lee, Jae-Hyuk Eoh, Seok-Kwon Son, Jong-Bum Kim, and Ji-Young Jeong(KAERI) PDF보기 PPT보기
2016-Spring 1E : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 14:50 203 (2F) Safety Analysis for Loss of Flow Related to Loss of Off-site Power in PGSFR Jae-Ho Jeong, Kwi-Lim Lee, Chi-Woong Choi, Tae-Kyung Jeong, and Kwi-Seok Ha(KAERI) PDF보기 -
Last Modified : 1998-Autumn