학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2023-Spring | 3D : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.18(Thu) 13:00 | Lobby (3F) | Criticality Safety Analysis(CSA) for the Shifted Fuel Assemblies in Spent Fuel Transportation Cask | Yubin Go, Kyoon Ho Cha, Chang Je Park, Hyuk Han, Keonil Cha, and Seung Uk Yoo(Sejong Univ.) | PDF보기 | - |
| 2023-Spring | 3D : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.18(Thu) 13:00 | Lobby (3F) | Criticality Safety Effect according to Fuel Rod Consolidation | Kiyoung Kim and Kyungho Roh(KHNP CRI) | PDF보기 | - |
| 2023-Spring | 3D : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.18(Thu) 13:00 | Lobby (3F) | Analysis of Hydrogen Isotopes in Consumer Goods Using High Precision Gas Mass Spectrometry | Jeong Eun Kim(KAERI), Min Jun Kim, and Bong Gi Kim(KINS), Jin Bok Lee Jin Seog Kim, and Kiryong Hong(KRISS) | PDF보기 | PPT보기 |
| 2023-Spring | 3D : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.18(Thu) 13:00 | Lobby (3F) | Synthesis and Characterization of Stable Ag+ Ion Clusters | Jeong Woo Hong, Sohyeon Lim, Chang Hyuk Kang, Chung Hun Han, and Hee-Jung Im(JNU) | PDF보기 | - |
| 2023-Spring | 3D : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.18(Thu) 13:00 | Lobby (3F) | Surface Reactivities of U(IV) Nanoparticles in Aqueous Phases | Wansik Cha, Seonggyu Choi, Hyejin Cho, and Hye-Ryun Cho(KAERI) | PDF보기 | - |
| 2023-Spring | 3D : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.18(Thu) 13:00 | Lobby (3F) | Analysis of 99Tc in Radioactive Waste by ICP-MS | Jung-Weon Choi, Kwangsoon Choi, Gi Yong Kim, Jihyun Kim, and Jung Bo Yoo(KAERI) | PDF보기 | - |
| 2023-Spring | 3D : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.18(Thu) 13:00 | Lobby (3F) | The Need for Performance Evaluation prior to Direct Use of Commercial Resin | JUNG BO YOO and HYO JIN AHN(KAERI) | PDF보기 | - |
| 2023-Spring | 3D : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.18(Thu) 13:00 | Lobby (3F) | A Study on Assessment System for the Integrity of Spent Nuclear Fuel under Normal Conditions of Transport | Woo-seok Choi, JaeHoon Lim, Jongmin Lim, and Gil-Eon Jeong(KAERI) | PDF보기 | - |
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 09:00 | 202B (2F) | Post-quench Ductility of Cr-coated (8μm, AIP) Zr-1.1Nb Accident Tolerant Fuel Cladding and Accident Margin Analysis | SungHoon Joung and Youho Lee(SNU) | PDF보기 | - |
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 09:20 | 202B (2F) | Thermo-mechanical Analysis of Multi-layered Accident-tolerant fuel (ATF) Claddings | Jiwon Mun, Hyeong-Jin Kim, and Ho Jin Ryu(KAIST) | PDF보기 | - |
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 09:40 | 202B (2F) | Numerical Investigation of Creep Behavior of Cr-coated ATF under Steady-state Condition | Jinsu Kim, Hyuntaek Rho, and Youho Lee(SNU) | PDF보기 | - |
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 10:00 | 202B (2F) | 2D FDM Structural Analysis Model for Cr-coated ATF Cladding: Development and Implementation into Fuel Analysis Code | Hyuntaek Rho and Youho Lee(SNU) | PDF보기 | PPT보기 |
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 10:20 | 202B (2F) | Development and Evaluation of Cold Spray Cr-coated Zr-alloy Cladding as Accident Tolerant Fuel (ATF) Design in LWRs | Hwasung Yeom(POSTECH), Kumar Sridharan(University of Wisconsin-Madison) | PDF보기 | - |
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 11:00 | 202B (2F) | Effects of Acoustic Impedance on Spent Nuclear Fuel Ultrasonic Inspection | Kyung Gun Kim and Jin Ho Jeong(KHNP) | PDF보기 | - |
| 2023-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 11:20 | 202B (2F) | Exploring the Microstructural Difference Between Circumferential Hydride and Radial Hydride in Reactor-grade Zirconium Cladding Tube | Dahyeon Woo and Youho Lee(SNU), Joo-Hee Kang(KIMS) | PDF보기 | - |
Last Modified : 1998-Autumn
