학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Preliminary Experimental Evaluation of Natural Convection Loop for Liquid Gallium | Sarah Kang, Seung Won Lee, Sung Dae Park, In Cheol Bang, and Ji Hyun Kim(UNIST) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Hydraulic Test for Sump Strainer of ECCS Recirculation | Jun Seok Park and Sang-Nyung Kim(KHU) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A CFD Simulation of a 1/5-Scale Steam Generator Simulator | Hwang Bae, Dongjin Euh, Byungsoo Shin, Yungjoo Ko, and Tae Soon Kwon(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Design Concept of a 1/5-Scale Core Simulator | Hwang Bae, Dongjin Euh, Byungsoo Shin, Yungjoo Ko, and Tae-Soon Kwon(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A CFD Simulation for a Design of Core Flow Simulator for SMART | Yung Joo Ko, Hwang Bae, Dong Jin Euh, and Tae Soon Kwon(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Investigation of Characteristics of Impinging Jet for 1/5-Scale ECC Injection | Byung Soo Shin, Yung Joo Ko, Hwang Bae, and Tae Soon Kwon(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 1/5-Scale Air Water Test for ECC Bypass | Byung Soo Shin, Hwang Bae, Yung Joo Ko, and Tae Soon Kwon(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Development of a Measurement Technique for Droplets During Reflood | Byoung Jae Kim, Hyung Kyu Cho, and Sang Ki Moon(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Performance Comparison of Deflector and DVI+ Duct | Tae-Soon Kwon, Seungtae Lee, and Chul-Hwa Song(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Experimental Study on Flooding Phenomenon | Yong Jin Kim(KAIST) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A Preliminary Study on the Propagation of RCP Pressure Perturbation into Reactor Vessel Downcomer | In-Cheol Chu, Jung Taek Kim, Tae Soon Kwon, and Chul-Hwa Song(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Experimental Study of ECC Duct Bypass for Development of an Advanced DVI+ | Seungtae Lee, Young Jung Yun, Dongjin Euh, and Tae-Soon Kwon(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Measurement of the Superheated Steam Temperature in a Post-CHF Dispersed Droplet Flow Regime | Seok Cho, Sang-Ki Moon, Hyung-Kyu Cho, Young-Jung Yun, Jeong-Kuk Park, Chul-Hwa Song, and Won-Pil Ba | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | 3D Analysis of Cooling Performance with Loss of Offsite Power Using GOTIHIC Code | Kyemin Oh and Gyunyoung Heo(KHU) Insik Na(ACT Co., Ltd.) Yujung Choi(KHNP) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Fretting Wear Experiments between the Same Alloy 690 Materials for Conservative Wear Evaluation of Steam Generator Tube | Jeong-Keun Lee and Chi-Yong Park(KEPRI) | PDF보기 | - |
Last Modified : 1998-Autumn
