학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2022-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.19(Thu) 13:00 | 로비 (3F) | Performance Evaluation of Pulse Shape Discrimination Based on CCM and CNN According to Light Output Threshold | Seonkwang Yoon and Ho-Dong Kim(UST), Chaehun Lee, Byung-Hee Won, Seong-Kyu Ahn, and Sang-Bum Hong(KAERI), Hee Seo(JBNU) | PDF보기 | - |
| 2022-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.19(Thu) 13:00 | 로비 (3F) | Integrity Evaluation of Neutron Absorber for Spent Nuclear Fuel Racks Using Boron-10 Areal Density Analysis Method | Hwasoo Kang, Jongho Hong, and Jaechoon Lee(KHNP), Donghee Lee and Kiyoung Kim(KHNP CRI) | PDF보기 | - |
| 2022-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.19(Thu) 13:00 | 로비 (3F) | Performance Assessment of Automatic Continuous Separating System for Radiochemical Analysis | Heewon Kim, Chae-Yeon Lee, Ga Hyun Kim, Sang-Do Choi, Jong-Myoung Lim, and Hyuncheol Kim(KAERI) | PDF보기 | - |
| 2022-Spring | 3C : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) | 5.19(Thu) 13:00 | 로비 (3F) | Influence of Rotating Speed on the Electrodeposition of ZrCl Metal with using a Rotating Cylinder Electrode | Seungmin Ohk, Jungho Hur, Galam Seo, Hongjeong Lee, Hyeonjune Noh, and Jaeyeong Park(UNIST) | PDF보기 | - |
| 2022-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 09:00 | 삼다홀B (3F) | Modeling the Effect of Soluble Group I Fission Isotope (Rb, Cs) Chlorides on the Phase Behavior of Multi Component Molten Salt Reactor Chloride Fuels | Woei Jer Ng and Ho Jin Ryu(KAIST) | PDF보기 | PPT보기 |
| 2022-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 09:20 | 삼다홀B (3F) | Enhanced Fabrication of UN Pellet from U2N3 Powder using Spark Plasma Sintering | Jungsu Ahn and Sangjoon Ahn(UNIST) | PDF보기 | - |
| 2022-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 09:40 | 삼다홀B (3F) | Doped UO2 Pellet Technology for Advanced Technology Fuels | Jae Ho Yang, Dong Joo Kim, Dong Seok Kim, and Dae Ho Kim(KAERI) | PDF보기 | - |
| 2022-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 10:00 | 삼다홀B (3F) | Development of Transient Fuel Performance Analysis System for Ultra Long-life Micro Lead-cooled Fast Reactor | Jiwon Mun and Ho Jin Ryu(KAIST) | PDF보기 | - |
| 2022-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 10:20 | 삼다홀B (3F) | Energy-balance Model of Axial Fuel Relocation Under LOCA | JangSoo OH, SungUk LEE, and YongSik Yang(KAERI) | PDF보기 | - |
| 2022-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 10:40 | 삼다홀B (3F) | First Principles Calculations of Cohesive Energy of Fission-Product-Segregated Grain Boundary of UO2 | Jae Joon Kim, Hyun Woo Seong, and Ho Jin Ryu(KAIST) | PDF보기 | - |
| 2022-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 11:00 | 삼다홀B (3F) | Development and Validation of Cr Diffusion Model for Coated Zircaloy Accident Tolerant Fuel Cladding | Dongju Kim and Youho Lee(SNU) | PDF보기 | - |
| 2022-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 11:20 | 삼다홀B (3F) | Evaluation of Power to Burst during LOCA in APR1400 by FAMILY Code | Joosuk Lee, Young-Seok Bang, and Kyunglok Baek(KINS) | PDF보기 | - |
| 2022-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 11:40 | 삼다홀B (3F) | Understanding Mechanical Integrity Zircaloy with Radial Hydrides Via Image Analysis of Hydride Morphology | Dahyeon Woo and Youho Lee(SNU) | PDF보기 | - |
| 2022-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 12:00 | 삼다홀B (3F) | Areas of Improvement in FRAPCON and FRAPTRAN Codes for Applications to Fuels with Cladding Material Change | Ju Yeop Park, Sarah Kang, Seulbeen Kim, Hyedong Jeong, and Kyunglok Baek(KINS) | PDF보기 | PPT보기 |
| 2022-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 13:30 | 삼다홀B (3F) | Post-irradiation Microstructural Characterization on 3.5-MeV Self-ion Irradiated Ferritic/Martensitic Steels at a Radiation Damage Level of 480 dpa | Myeongkyu Lee, Jungsu Ahn, and Sangjoon Ahn(UNIST) | PDF보기 | - |
Last Modified : 1998-Autumn
