학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2017-Spring | 1C : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 10:00 | 203 (2F) | Design evaluations of high temperature piping system in sodium test facility | Seok-Kwon Son(KAERI), Hyeong-Yeon Lee(KAERI), and Ji-Young Jeong(KAERI) | PDF보기 | PPT보기 |
| 2017-Spring | 1C : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 10:20 | 203 (2F) | Debris Bed Analysis in Discharge of the Molten Fuel?through Lower Structure of Fuel Assembly in PGSFR | Min Ho Lee(UNIST), Hyo Heo(UNIST), Dong Wook Jerng(CAU), and In Cheol Bang(UNIST) | PDF보기 | - |
| 2017-Spring | 1C : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 11:00 | 203 (2F) | Measurements of Enhanced Mixing with U-pattern Wire Wrap Spacer in 19-pin Rod Bundle Using Particle Image Velocimetry | Yeong Shin Jeong(UNIST), Ji Yong Kim(UNIST), and In Cheol Bang(UNIST) | PDF보기 | - |
| 2017-Spring | 1C : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 11:20 | 203 (2F) | Experimental Study on Natural Convection Air Flow Characteristics in a Finned-tube type Sodium-to-Air Heat Exchanger System | Jaehong Min(CNU), Hyungmo Kim(KAERI), Jaehyuk Eoh(KAERI), Weon Gyu Shin (CNU), and Ji-Young Jeong(KAERI) | PDF보기 | PPT보기 |
| 2017-Spring | 1C : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 11:40 | 203 (2F) | Estimation of Ultrasonic Beam Profile Radiated from a Plate-Type Ultrasonic Waveguide Sesnor in Sodium | Sang-Jin Park(KAERI), Hoe-Woong Kim(KAERI), Young-Sang Joo(KAERI), Sung-Kyun Kim(KAERI), and Jong-Bum Kim(KAERI) | PDF보기 | - |
| 2017-Spring | 1D : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 13:30 | 203 (2F) | Development and Verification of Siphon Breaker Simulation Program | Kwon-Yeong Lee(HGU) and Wan-Soo Kim(HGU) | PDF보기 | - |
| 2017-Spring | 1D : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 13:50 | 203 (2F) | Design for Joint module of NTD Hydraulic Rotation Device | Joon Yong Chang(KAERI), Ki Jung Park(KAERI), Seong Hoon Kim(KAERI), Dae Young Chi(KAERI), and Cheol Park(KAERI) | PDF보기 | - |
| 2017-Spring | 1D : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 14:10 | 203 (2F) | Preliminary Safety Classification of SSCs for a Pool-Type Research Reactor | Suki Park(KAERI) | PDF보기 | - |
| 2017-Spring | 1D : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 14:30 | 203 (2F) | A Study of Residence Time Distributions Using Various Numerical Methods | Minkyu Jung(KAERI), Kyoungwoo Seo(KAERI), Daeyoung Chi(KAERI), Seonghoon Kim(KAERI), and Cheol Park(KAERI) | PDF보기 | - |
| 2017-Spring | 1D : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 14:50 | 203 (2F) | Beyond-design-basis Accident Analysis using Bayesian Network: Application to Research Reactor | Shinyoung Kwag(KAERI), Jinho Oh (KAERI), and Jong-Min Lee(KAERI) | PDF보기 | - |
| 2017-Spring | 1D : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 15:30 | 203 (2F) | A Study on Securing Core Cooling Ability in Case of Total Loss of Feedwater for 2-Loop Westinghouse NPP | Seung-Chan Lee(KHNP CRI) and Young-Chan Park(ACT Co., Ltd.) | PDF보기 | - |
| 2017-Spring | 1D : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 15:50 | 203 (2F) | Sensitivity Analysis on Pressurizer Safety Valve Capacity for Overpressure Protection of Integral Reactor | Minkyu Lee(KAERI), June Woo Kee(KAERI), Seungyeob Ryu(KAERI), Juhyeon Yoon(KAERI), and Young In Kim(KAERI) | PDF보기 | - |
| 2017-Spring | 1D : 원자로시스템기술 (Reactor System Technology) | 5.19(Fri) 16:10 | 203 (2F) | Preliminary Study of Conceptual Design of the ATOM Safety System | Gwang Hyeok Seo(HYU), Doyoung Shin(HYU), Hong Hyun Son(HYU), and Sung Joong Kim(HYU) | PDF보기 | - |
| 2017-Spring | 1E : 원자로시스템기술 (Reactor System Technology) | 5.18(Thu) 13:00 | 로비 (3F) | A Study on Critical Water Level during Mid-Loop Operation | Seonggi Jeong(KEPCO E&C), Kunwoo Yi(KEPCO E&C), Byung Ryul Jung(KEPCO E&C), Yong Sang Ko(KEPCO E&C), Yoon Jae Choe(KEPCO E&C), Seok Jeong Yune(KEPCO E&C), and Seong Chan Park(KEPCO E&C) | PDF보기 | - |
| 2017-Spring | 1E : 원자로시스템기술 (Reactor System Technology) | 5.18(Thu) 13:00 | 로비 (3F) | Advisory Committee on Reactor Safeguards Review of Reactor for the APR1400 Design Certification | Jeong-kwan Suh(KHNP CRI) and Yun-ho Kim(KHNP CRI) | PDF보기 | - |
Last Modified : 1998-Autumn
