학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2019-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.23(Thu) 13:00 | 로비 (3F) | Thermal Analysis of HISTORM-100 Dry Storage Cask with Heterogeneous WH14X14 Fuel Assembly using COMSOL MULTIPHYSICS Program | SunWoo Park and KwangHeon Park(KHU) | PDF보기 | - |
| 2019-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.23(Thu) 13:00 | 로비 (3F) | A Criticality Analysis of the Misloading Assemblies in the 32 Burnup Credit Cask | Seung Uk Yoo, Hyuk Han, Ye Ji Yune, and Chang Je Park(Sejong Univ.) | PDF보기 | - |
| 2019-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.23(Thu) 13:00 | 로비 (3F) | Analysis for Thermal Test Assessment Method of Spent Fuel Concrete Cask Using a Scale Down Model | Ju-Chan Lee, Kyung-Sik Bang, Seung-Hwan Yu, and Woo-Seok Choi(KAERI), Sungho Ko(CNU) | PDF보기 | - |
| 2019-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.23(Thu) 13:00 | 로비 (3F) | A study of Sensitivity of Partial Defect Detection Capability Using Scintillator-photodiode Detector with 17x17 Spent Fuel Assemblies | Yeongjun Kim and ManSung Yim(KAIST) | PDF보기 | - |
| 2019-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.23(Thu) 13:00 | 로비 (3F) | Inflience of Ce(3+) Cation on Structural Property of Uraniun Dioxide | Dong Woo Lee, Jeongmook Lee, Jong-Yun Kim, and Sang Ho Lim(KAERI) | PDF보기 | - |
| 2019-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.23(Thu) 13:00 | 로비 (3F) | Criticality Safety Review using WIMS-AECL Code in CANDU6 Spent Fuel Pool | Donghwan Park and Youngae Kim(KHNP CRI) | PDF보기 | - |
| 2019-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.23(Thu) 13:00 | 로비 (3F) | Measurement of Neutron Shielding Materials Property for the Spent Fuel Cask | Minsu Ju and Jinyoung Chung(BRNC), Teahoon Jeon and Jungho Song(Orbitech), Sungkug Hwang and Yeonoh Lee(SeAH), Kevin Ray Ayag and Hongdoo Kim(KHU) | PDF보기 | - |
| 2019-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.23(Thu) 13:00 | 로비 (3F) | Laser-induced Breakdown Spectroscopy for in-situ Analysis of Nuclear Materials: Aqueous Solution | Yunu Lee and Sungyeol Choi(KAIST) | PDF보기 | - |
| 2019-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.23(Thu) 09:00 | 201A (2F) | The Stability of Cr Alloy Coating Layer under Mechanical Contact and High Temperature Steam at 1200 °C | Young-Ho Lee, Jung-Hwan Park, Il-Hyun Kim, Dong-Jun Park, Yang-Il Jung, Byoung-Kwon Choi, and Hyun-Gil Kim(KAERI) | PDF보기 | - |
| 2019-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.23(Thu) 09:20 | 201A (2F) | Progress of Accident Tolerant Fe-based Alloy Cladding Development at KEPCO NF | Hun Jang, Sung-yong Lee, Dae Gyun Ko, Chae-ho Lim, Chan Do Jung, Yoon Ho Kim, and Seung Jae Lee(KEPCO NF), Hyunmyung Kim, Chaewon Kim, and Changheui Jang(KAIST) | PDF보기 | - |
| 2019-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.23(Thu) 09:40 | 201A (2F) | Technology Development of Barrier Cladding for the Metal Fuel | Jun Hwan Kim, Sunghwan Yeo, Sung Ho Eom, Sung Ho Kim, and Jeong Yong Park(KAERI), Min Soo Lee and Tai Hong Yim(KITECH) | PDF보기 | - |
| 2019-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.23(Thu) 10:00 | 201A (2F) | Study of Annular Fuel Fabrication Technology in a Viewpoint of Microstructure | Sang-Gyu Park, Kiho Kim, and Jeong-Yong Park(KAERI) | PDF보기 | - |
| 2019-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.23(Thu) 10:40 | 201A (2F) | Characterization of U-10wt.%Zr-5wt.%RE Fuel Slugs Recycling Metallic Fuel Scrap | Seung-Uk Mun and Sun-Ig Hong(CNU), Ki-Hwan Kim and Seoung-Woo Kuk(KAERI) | PDF보기 | - |
| 2019-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.23(Thu) 11:00 | 201A (2F) | Reactivity Evaluation of U-Zr Melt Residue after Melting in the Graphite Crucible | Seong-Jun Ha and Young-Kook Lee(Yonsei Univ.), Jeong-Yong Park and Seoung-Woo Kuk(KAERI) | PDF보기 | - |
| 2019-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.23(Thu) 11:20 | 201A (2F) | Aspect of Breakaway Oxidation of a Zirconium Alloy Cladding Tube during Oxidation at 800 ºC | Cheol Min Lee and Young-Soo Han(KAERI), Gwan Yoon Jeong and Dong-Seong Sohn(UNIST) | PDF보기 | - |
Last Modified : 1998-Autumn
