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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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 -
2016-Spring 1E : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 15:30 203 (2F) Performance Evaluation of Sodium-to-Sodium Heat Exchangers in STELLA-2 Youngchul Jo(KAERI), Seok-kwon Son(KAERI), Jung Yoon(KAERI), and Jiyoung Jeong(KAERI) PDF보기 -
2016-Spring 1E : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 15:50 203 (2F) Combined Safety Analysis on Gallium-based Passive Decay Heat Removal System of Ultra-long Cycle Fast Reactor Seok Bin Seo, In Guk Kim, and In Cheol Bang(UNIST) PDF보기 -
2016-Spring 1E : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 16:10 203 (2F) Reactor Vault Cooling System (RVCS) Effect on ULOHS Event for the Prototpe Gen-IV SFR Chiwoong Choi, Kwiseok Ha, Taekyeong Jeong, Jaeho Jeong, Kwilim Lee, Seungwon Lee, and Sangjun An(KAERI) PDF보기 -
2016-Spring 1E : 원자로시스템기술 (Reactor System Technology) 5.13(Fri) 16:30 203 (2F) Melt Fragmentation Characteristics of Metal Fuel with Melt Injection Mass during Initiating Phase of SFR Severe Accidents Hyo Heo, Min Ho Lee, and In Cheol Bang(UNIST), Dong Wook Jerng(CAU) PDF보기 -
Last Modified : 1998-Autumn