학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2024-Autumn | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.24(Thu) 13:00 | 컨벤션홀 I | Corrosion Characteristics Evaluation on Structural Materials in NaCl-MgCl2 Molten Salt | Seok Min Yoon and Seol Kim(UST), Taeho Kim, Eun-Young Choi, and Chang Hwa Lee(KAERI) | PDF보기 | - |
| 2024-Autumn | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.24(Thu) 13:00 | 컨벤션홀 I | Characteristics of the Heat-Affected Zone of Metal-Clad Structural Materials for Molten Salt Reactor | Ji-Hyun Yoon and Giseung Shin(KAERI), Jeoung Han Kim(Hanbat National Univ.) | PDF보기 | - |
| 2024-Autumn | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.24(Thu) 13:00 | 컨벤션홀 I | Corrosion Mechanism Analysis of Ni and Ni Model Alloy on Molten Chloride Salt | Hyeon-Geun Lee, Chaewon Kim, Jung-Min Kim, and Daejong Kim(KAERI) | PDF보기 | - |
| 2024-Autumn | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.24(Thu) 13:00 | 컨벤션홀 I | Corrosion Behavior of Ni-201 in High-Temperature NaCl+MgCl2 Molten Salt for Next-Generation Molten Salt Reactor | Won Chan Lee, Seung Ju Nam, and Jeoung Han Kim(Hanbat National Univ.), Seong Sik Hwang, Jeon Soon Jeon, and Ji Hyun Yoon(KAERI) | PDF보기 | - |
| 2024-Autumn | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.24(Thu) 13:00 | 컨벤션홀 I | A Study on Dynamic Impact Analysis of Simplified Spacer Grid Designed for 24-Finger and 28-Finger Control Rods | Joo-Young Ryu, Kyoung-Hong Kim, Ba-Leum Kim, Dong-Geun Ha, and Yoon-Ho Kim(KEPCO NF) | PDF보기 | - |
| 2024-Autumn | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.24(Thu) 13:00 | 컨벤션홀 I | A Study on Finite Element Analysis of Seismic Response Considering Boundary Nonlinearity of Surface to Surface Contact | Dong-Hyun Kim, Hyun-Jung Kim, and Young-Wook Tahk(KAERI) | PDF보기 | - |
| 2024-Autumn | 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.24(Thu) 13:00 | 컨벤션홀 I | Comparison of Modeling Techniques for Simulating Contact Between Steam Generator Tubes and Supports | Dae Kyung Choi, Won Man Park, and Choengryul Choi(Elsoltec), Young-Jin Oh and Heejae Shin(KEPCO E&C) | PDF보기 | - |
| 2024-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 09:00 | 607 | Imitation of Boiling Curve Depending on the Different Control Modes using a Water Electrolysis | Jeonghun Seo, Seungju Lee, and Haekyun Park(Kyungpook National Univ.) | PDF보기 | PPT보기 |
| 2024-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 09:20 | 607 | Measurement of Active Nucleation Site Density according to Surface Roughness in a Water Electrolysis | Seungju Lee, Jeonghun Seo, and Haekyun Park(Kyungpook National Univ.) | PDF보기 | PPT보기 |
| 2024-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 09:40 | 607 | Comparison of Supercritical CO₂ Power System Surrogate Model to Test Data from KAIST ABC Test Loop | Gihyeon Kim, Jeong Yeol Baek, and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2024-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 10:00 | 607 | Effect of Filling Ratio on the Entrainment Limit of Large-Scale Heat Pipe with 3D-Printed Wick Structure | Faruk Celik, Dong Hun Lee, Ye Yeong Park, and In Cheol Bang(UNIST) | PDF보기 | PPT보기 |
| 2024-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 10:20 | 607 | Experiments on Release of Cold Thermal Energy by Mass Flow Rate of Packed Bed Cold Energy Storage System | Dahui Kwack, Chunsik Lee, and Choongsub Yoem(IAE) | PDF보기 | - |
| 2024-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 11:00 | 607 | Basic Design Methodogy for Helical Steam Generator of i-SMR Integral Effect Test Facility | Hwang Bae, Jin-Hwa Yang, Kyoung-Ho Kang, and Byong Guk Jeon(KAERI), Sang Gyun Nam and Byongjo Yun (PNU) | PDF보기 | - |
| 2024-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 11:20 | 607 | The Local Scaling Analysis for Experiments of the Helically Coiled Tube Steam Generator | Sang Gyun Nam, Seongbae Park, and Byongjo Yun, Hwang Bae and Seok Kim(KAERI) | PDF보기 | - |
| 2024-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 11:40 | 607 | Predicting Critical Heat Flux under Heaving Conditions: A Methodology Integrating Transient Conduction Calculation and CHF Mechanistic Model | Jin-Seong Yoo, Heepyo Hong, Hyukjae Ko, Ja Hyun Ku, Goon-Cherl Park, and Hyoung Kyu Cho(SNU) | PDF보기 | - |
Last Modified : 1998-Autumn
