| 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 |
|---|---|---|---|---|
| 3004107 | 核反應器工程 | Nuclear Reactor Engineering | 3.0 | 3 |
| 中文概述 Chinese Description | 本課程內容主要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)兩主要部份。熱流與安全分析內容包括核反應器系統描述、核能電廠熱力學，流體系統分析，核反應器熱的產生與熱流學，核反應器熱流與應力分析。 透過PRA技術可全面檢討核能電廠潛在弱點，並可依評估結果據以進行最有效益之改善，提昇核電機組營運安全。PRA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、風險管制、用過核燃料處置等之應用。 | |||
| 英文概述 English Description | This lecture will mainly covers the thermal-hydraulics and safety analyses and the modern methods for reliability and risk assessment for nuclear power plants (NPPs). Thermal hydraulics and safety analyses will covers: design of fission reactors; energy conversion in nuclear power systems; fluid flow system, thermal and structural analysis of reactor core and plant components; thermal-hydraulic analysis of accidents in nuclear power plants. The weakness of nuclear power plants can be identified through the PRA technology. Therefore, the safety feature of the associated SSCs (Structures, Systems, and Components) will be improved. Course content will cover 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, risk control, spent-fuel problems, etc. be addressed as well. | |||
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