학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2023-Autumn | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.26(Thu) 13:00 | Lobby (3F) | History and Current Status of the Development of the U3Si2 Atomization Process at KAERI | Jonghwan Kim, Jaedong Lee, Jungmin Park, Kinam Kim, and Yongjin Jeong(KAERI) | PDF보기 | - |
| 2023-Autumn | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.26(Thu) 13:00 | Lobby (3F) | Peening Effects on Surface Properties of Alloy 690 | Baosheng Bai, Sungyu Kim, Joonho Moon, and Chi Bum Bahn(PNU), Wongeun Yi(DOOSAN), Eunsub Yun(KHNP CRI) | PDF보기 | - |
| 2023-Autumn | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.26(Thu) 13:00 | Lobby (3F) | Formation of Selective Oxide Layer on FeCrAl Alloy Using Anodization for Nuclear Application | Jun Heo, Jae Young Im, and Sung Oh Cho(KAIST) | PDF보기 | - |
| 2023-Autumn | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.26(Thu) 13:00 | Lobby (3F) | Effect of Alloying Element in Nickel Alloy on Molten Chloride Salt Corrosion | Hyeon-Geun Lee, Chaewon Kim, Jung-Min Kim, Taeho Kim, and Daejong Kim(KAERI) | PDF보기 | - |
| 2023-Autumn | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.26(Thu) 13:00 | Lobby (3F) | Characteristics of Ni Cladded Type 316H Stainless Steel for Molten Salt Reactor Application | Ji-Hyun Yoon(KAERI), Jeoung Han Kim(Hanbat National Univ.) | PDF보기 | - |
| 2023-Autumn | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.26(Thu) 13:00 | Lobby (3F) | Development of Non-Destructive Evaluation System for Rod Cluster Control Assembly Using Magnetic Imaging Technology | Hyoung Tae Kim(KAERI), Kun Woo Kim and Duck-Gun Park(AIPIT), Jinyi Lee(CSU) | PDF보기 | - |
| 2023-Autumn | 4F : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.26(Thu) 13:00 | Lobby (3F) | Seismic Analysis of the Piping System with Shaking Table Test | ChiWoong Ra, Eun-ho Lee, Hyungyu Roh, Jeonghyun Kim, and No-cheol Park(Yonsei Univ.) | PDF보기 | - |
| 2023-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 09:00 | 202 (2F) | Evaluation of the Horizontal Condensation Heat Exchanger Analysis Methodology | Sang Gyun Nam, Youngjae Park, Seong-Su Jeon, and Soon-Joon Hong(FNC Tech.) | PDF보기 | - |
| 2023-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 09:20 | 202 (2F) | Calculation of Shell Side Pressure Drop in the Experiment Simulating Typical Heat Exchanger Using MULTID Component Model of MARS-KS Code | YOUNG SEOK BANG, JUNGJIN BANG, SEONG-SU JEON, BUB DONG CHUNG, and YOUNGSUK BANG(FNC Tech.) | PDF보기 | - |
| 2023-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 09:40 | 202 (2F) | Experimental Investigation of Helical Fin Effect on CHF Under the Inclined Condition | Chang Won Lee, Jin-Seong Yoo, Hee Pyo Hong, Goon-Cherl Park, and Hyoung Kyu Cho(SNU), Geon-Woo Kim(KINS) | PDF보기 | - |
| 2023-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 10:00 | 202 (2F) | Experimental Investigation of the Fouling Characteristics of the CRUD on Pressurized Water Reactor Operating Conditions | Ji Yong Kim, Yunju Lee, Byeongju Kim, Ji Hyun Kim, and In Cheol Bang(UNIST) | PDF보기 | - |
| 2023-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 10:40 | 202 (2F) | A Flow Boiling Heat Transfer Correlation of a Helically Coiled Tube | Min Gi Kim, Byongjo Yun, and Jae Jun Jeong(PNU) | PDF보기 | PPT보기 |
| 2023-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 11:00 | 202 (2F) | Experimental Observation of Heaving Motion Effect on CHF in Helical Finned Rod with Working Fluid of R134a | Jin-Seong Yoo, Chang Won Lee, Heepyo Hong, Hyukjae Ko, Ja Hyun Ku, Goon-Cherl Park, and Hyoung Kyu Cho(SNU) | PDF보기 | - |
| 2023-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 11:20 | 202 (2F) | Experimental Investigation of Hybrid Cesium Heat Pipe for Microreactor Applications | Dong Hun Lee and In Cheol Bang(UNIST) | PDF보기 | - |
| 2023-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 11:40 | 202 (2F) | Concept of a Heat Pipe Assembly Test for a Heat Pipe Cooled Space Reactor | Byung Ha Park, Chan Soo Kim, and SinYeob Kim(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
