학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | Reflood Phenomena in a 5x5 Ballooned Rod Bundle | Byoung Jae Kim, Jong Rok Kim, Kihwan Kim, and S. K. Moon(KAERI) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | Numerical Simulation of Fluid Mixing In Upper Annular Space of SMART during Early Stage of Non-LOCA | Youngmin Bae, Young-In Kim, and Keung Koo Kim(KAERI) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | Implementation of a Model of Turbulence into a System Code, GAMMA+ | Hyeonil Kim and Hong-Sik Lim(KAERI) Hee-Cheon No(KAIST) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | Assessment Using ANL Experiments on Void Fraction in a Vertical Tube | KyuHyun Han and YoungSeok Bang(KINS) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | The Effect of the Holes Size Change of Lower-Support-Structure-Bottom Plate on the Reactor Core-Inlet Flow-Distribution | Gong Hee Lee, Young Seok Bang, and Ae Ju Cheong(KINS) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | Thermal-hydraulic Analysis and Code Assessment for Reactor Vessel Upper-head Small Break LOCA Using SPACE Code | Minhee Kim and Seyun Kim(KHNP CRI) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | Lunar Nuclear Power Plant Design for Thermal-Hydraulic Cooling in Nano-Scale Environment: Nuclear Engineering-based Interdisciplinary Nanotechnology | Tae Ho Woo(Systemix Global Co., Ltd.) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | Assessments of UCB-Kuhn Condensation Tests by Various Thermal-Hydraulic Codes | Ju Yeop Park(KINS) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | A Preliminary Study on the Reconstruction Algorithm of the Bubble Size to Inspect Twophase Flows Using Single Cone-beam X-ray | Che Wook YIM, Song Hyun KIM, and Chang Ho SHIN(HYU) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | Determination of Initial Conditions for the Safety Analysis by Random Sampling of Operating Parameters | Hae-Yong Jeong and Moon-Ghu Park(Sejong Univ.) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | k-ε Turbulence Modeling in the CUPID Code for Natural Convection | Seung-Jun Lee, Ik Kyu Park, and Han Young Yoon(KAERI) Jungwoo Kim(Seoultech) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | Numerical Analysis of APR1400 Steam Generator by CUPID/MARS Heat Structure Coupling | Jae Ryong Lee, Seung Jun Lee, lk Kyu Park, and Han Young Yoon(KAERI) Hyoung Kyu Cho(SNU) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | A Study on the Optimization Method of the Main Steam Safety Valve Characteristics for Overpressure Protection | Kyoung Ryun Kim, Ung Soo Kim, Min Soo Park, Gyu Cheon Lee, and Shin Whan Kim(KEPCO E&C) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | Integrity Analysis of Turbine Building for the MSLB Using GOTHIC Code for Wolsong NPP Unit 2 | Bong-Jin Ko, Dong-Sik Jin, Jong-Hyun Kim, and Sang-Koo Han(ACT Co., Ltd.) Choi Hoon, Dong-Wook Kho(KHNP CRI) | PDF보기 | - |
| 2015-Spring | 5L : 원자력열수력 및 안전-Poster(Thermal Hydraulics and Safety) | 5.7(Thu) 13:00 ~ 15:00 | 3층 로비 | Comparative Study of Thermal Hydraulic Analysis Codes for Pressurized Water Reactors | Yang Hoon Kim, Mi Suk Jang, and Kee Soo Han(NESS) | PDF보기 | - |
Last Modified : 1998-Autumn
