학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2017-Autumn | 1C : 원자로시스템기술 (Reactor System Technology) | 10.27(Fri) 11:00 | 팔래스 (B2F) | Dynamic Simulation Modeling and Analysis of Under-sodium Fuel during In-vessel Transfer Motions | Youn-Hee Kwon(KAERI), Dong-Won Lim(KAERI), and Sung-Kyun Kim(KAERI) | PDF보기 | PPT보기 |
| 2017-Autumn | 1C : 원자로시스템기술 (Reactor System Technology) | 10.27(Fri) 11:20 | 팔래스 (B2F) | Evaluation on cooling performance of vessel air cooling system with flow guide for STELLA-2 | Sang-Min Park(KAERI), Youngchul Jo(KAERI), Jaehyuk Eoh(KAERI), Jung Yoon(KAERI), Hyungmo Kim(KAERI), and Ji-Young Jeong(KAERI) | PDF보기 | - |
| 2017-Autumn | 1C : 원자로시스템기술 (Reactor System Technology) | 10.27(Fri) 11:40 | 팔래스 (B2F) | Study of supercritical gas mixture power cycle application to the nuclear system | Seungjoon Baik(KAIST) and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 크리스탈 (B1F) | Analysis Methodology of Reactor Vessel Internal Flow using Flow Network Model | Dong Hwa Jeong(KEPCO E&C), Ho Cheol Jang(KEPCO E&C), Byung Ryul Jung(KEPCO E&C), and Seong Chan Park(KEPCO E&C) | PDF보기 | - |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 제이드 (B1F) | ASME Code Stress Evaluation of Re-engineered Primary Inlet Nozzle of APR1400 Steam Generator | Francis C. Kevore(KINGS) and Ihn Namgung(KINGS) | PDF보기 | - |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 제이드 (B1F) | APR1400 SG Support Stress Evaluation According to ASME BPVC Section III subsection NB and NF | Sang Q. Mai(KINGS) and Ihn Namgung(KINGS) | PDF보기 | - |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 제이드 (B1F) | Evaluation of Blast Wave Effects on Reactor Coolant System | Jung Yong Kim(KEPCO E&C), In Yong Kim(KEPCO E&C), Jang Hwan Jheon(KEPCO E&C), Ki Kwang Sung(KEPCO E&C), and Hyun Min Kim(KEPCO E&C) | PDF보기 | - |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 제이드 (B1F) | Comparative Analysis of FAST-2 and MATRA-S Code Using Validation Problem | Hyuk Kwon(KAERI), Seoung-Jin Kim(KAERI), Ju Hyung Lee(KAERI), Kyong-Won Seo(KAERI), and Dae-Hyun Hwang(KAERI) | PDF보기 | - |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 제이드 (B1F) | Preliminary Study of Single Phase Natural Circulation Flow Instability in Multiple Parallel-Channel Systems with RELAP5/MOD3 | Ki Moon Park(KAIST) and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 제이드 (B1F) | A Preliminary Core Design of the Space Nuclear Reactor | Saed Alrawash(Sejong Univ.), Boravy Muth(Sejong Univ.), Hong Yeop Choi(Sejong Univ.), Chang Je Park(Sejong Univ.) | PDF보기 | - |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 제이드 (B1F) | Flow mal-distribution and Maximum Crossflow Analysis on a basis of Fuel Assemblies in SMART core | Juhyung Lee(KAERI), S. J. Kim(KAERI), K. W. Seo(KAERI), H. Kwon(KAERI), and D. H. Hwang(KAERI) | PDF보기 | - |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 제이드 (B1F) | A CFD investigation of Using an Isothermal Compressor in a Supercritical CO2 Cycle for SMART Applications | Jin Young Heo(KAIST), Seong Gu Kim(KAIST), and Jeong Ik Lee(KAIST) | PDF보기 | PPT보기 |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 제이드 (B1F) | Conceptual Design of the Primary Cooling System Pump in Consideration of the Variable Flow Rate in the Research Reactor | Hyun-Gi Yoon(KAERI) and Kyoung-Woo Seo(KAERI) | PDF보기 | - |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 다이아몬드 (B1F) | Design, Fabrication and Characteristics Experiment of a Hybrid Fuel Locking Device for Upward Flow Core-Research Reactor | hyung huh(KAERI), yeong-garp cho(KAERI), yeon-sik yoo(KAERI), and kyong-ho kim(KAERI) | PDF보기 | - |
| 2017-Autumn | 1D : 원자로시스템기술 (Reactor System Technology) | 10.26(Thu) 13:00 | 다이아몬드 (B1F) | In-pipe Pressure Design Guideline for Downward Forced Flow Cooling System in Research Reactor ? | Ki-Jung Park(KAERI), Sunil Lee(KAERI), and Kyoungwoo Seo(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
