학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 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 | - |
| 2022-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 13:50 | 삼다홀B (3F) | Machine Learning Potential for Accurate Radiation Defect Simulations in Bcc-Fe | Sehyeok Park and Takuji Oda(SNU) | PDF보기 | - |
| 2022-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 14:10 | 삼다홀B (3F) | Estimation of Radiation Damage and Gaseous Ion Accumulation in Neutron Absorbers | Geon Kim, Eisung Yoon, and Sangjoon Ahn(UNIST) | PDF보기 | - |
| 2022-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 14:30 | 삼다홀B (3F) | Development of Machine-Learning Potential for Sodium Combustion Simulations: Tests for Basic Properties of Liquid Na, Solid Na2O, and Interfaces | Chaeyeong Kim and Takuji Oda(SNU) | PDF보기 | - |
| 2022-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 14:50 | 삼다홀B (3F) | Residual Stress Evaluation for Dissimilar Metals Welding Using Deep Fuzzy Neural Networks with Rule Dropout | Ji Hun Park, Hye Seon Jo, and Man Gyun Na(CSU) | PDF보기 | - |
| 2022-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.19(Thu) 13:30 | 300호 (3F) | Evaluation Method of Thermal Properties of Fuel Deposits Simulated in PWR Primary Water Condition | Hee-Sang Shim, Hye Min Park, Hyeong Wook Kim, and Do Haeng Hur(KAERI), Young-KooK Lee(Yonsei Univ.), Jeongho Han(HYU) | PDF보기 | - |
Last Modified : 1998-Autumn
