| 課程編碼 Course Code | 中文課程名稱 Course Name (Chinese) | 英文課程名稱 Course Name (English) | 總學分數 Credits | 總時數 Hours |
|---|---|---|---|---|
| 5605083 | 核能安全 | Nuclear Power Reactor Safety | 3.0 | 3 |
| 中文概述 Chinese Description | 本課程主要內容包括:核能電廠系統熱流與安全分析、量化風險評估(Probabilistic Risk Assessment, 簡稱PRA)兩個主要部份。 核能安全相關議題如，核反應器熱的產生、熱流與應力分析，核反應器重要系統與組件，核能電廠事故分析，核能電廠的環境輻射劑量。 PRA技術可全面檢討核能電廠潛在弱點，提昇核電機組營運安全。內容包括基本機率理論介紹、隨機變數與分佈函數、可靠度方法論、事件樹與故障樹分析、不準度分析及傳播等方法。並將包括PRA技術在核能電廠系統之應用。 | |||
| 英文概述 English Description | This lecture will mainly covers the thermal-hydraulics and safety analyses and the methods for probability of risk assessment (PRA) for nuclear power plants. Thermal hydraulics and safety analyses will includes: design of fission reactors; energy conversion in nuclear power systems; fluid flow system, thermal and structural analysis of reactor core. The weakness of nuclear power plants can be identified through the PRA technology. Therefore, the safety feature of the associated structures of systems and components will be improved. Lecture would include basic concept of probability, random variables and distribution functions, applications to the reliability assessment of components, event-tree and fault-tree analysis, uncertainty analysis and its propagation, etc. Examples and applications in nuclear plants will be addressed as well. | |||
備註：