| 著作 |
| 編號 | 2 |
| 期刊或研討會名稱 | Progress in Nuclear Energy , 地點: |
| 著作名稱 | Tolerance assessment and crack growth of chloride-induced stress corrosion cracking for Chinshan dry storage system |
| 年度 | 2022 |
| 類別 | 期刊論文 |
| 摘要 | |
| 關鍵字 | CFD, Chinshan nuclear power plant, CISCC, Crack growth rate |
| 編號 | 4 |
| 期刊或研討會名稱 | Annals of Nuclear Energy , 地點: |
| 著作名稱 | Development of 3-D numerical methodology to investigate transient characteristics of fuel temperature and hydrated residual water during drying process of dry storage system |
| 年度 | 2022 |
| 類別 | 期刊論文 |
| 摘要 | |
| 關鍵字 | DSS, SNF, Hydrated residual water, Numerical method |
| 編號 | 1 |
| 期刊或研討會名稱 | Nuclear Technology , 地點: |
| 著作名稱 | Spent Nuclear Fuel Heatup Calculations Supporting Emergency Planning Exemption Using CFD Code |
| 年度 | 2022 |
| 類別 | 期刊論文 |
| 摘要 | |
| 關鍵字 | Computational fluid dynamics, Chinshan nuclear power plant, emergency plan exemption, spent fuel pool, zirconium fire |
| 編號 | 3 |
| 期刊或研討會名稱 | Progress in Nuclear Energy , 地點: |
| 著作名稱 | Evaluation of crack growth of chloride-induced stress corrosion cracking in dry storage system under different environmental conditions |
| 年度 | 2020 |
| 類別 | 期刊論文 |
| 摘要 | |
| 關鍵字 | CFD, Chinshan nuclear power plant, CISCC, Dry storage, Environments characterization |
| 編號 | 6 |
| 期刊或研討會名稱 | International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety, 地點:台灣 |
| 著作名稱 | Chloride-Induced Stress Corrosion Cracking Crack Growth Rate of Stainless Steel Canister for Concrete Cask under Marine Condition |
| 年度 | 2022 |
| 類別 | 會議論文 |
| 摘要 | |
| 關鍵字 | CFD, CISCC, CGR, Chinshan Nuclear Power Plant |
| 編號 | 7 |
| 期刊或研討會名稱 | International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety, 地點:台灣 |
| 著作名稱 | Numerically Evaluate Hydrated Residual Water Drying Process for Dry Storage System under Low Thermal Load Situation |
| 年度 | 2022 |
| 類別 | 會議論文 |
| 摘要 | |
| 關鍵字 | DSS, SNF, CFD, Residual Water |
| 編號 | 5 |
| 期刊或研討會名稱 | International Conference on Nuclear Engineering, 地點:日本 |
| 著作名稱 | RADIOLOGICAL SAFETY ASSESSMENT OF DECOMMISSIONING NUCLEAR POWER PLANTS USING THE RESRAD CODE |
| 年度 | 2019 |
| 類別 | 會議論文 |
| 摘要 | |
| 關鍵字 | RESRAD, DCGL, DSR, Nuclear Power Plants, Decommission |