早期由於電腦的限制，侷限了吾人對核能安全的分析，所以只能夠以CFD模擬流場來分析核能安全此為單向流固耦合(one way coupling)。近年來，由於電腦運算能力的提升，雙向流固耦合(two way coupling)的分析方法已變為可能，使得流沖振動等分析更接近真實的物理現象。此外，由於大眾對於核能安全的需求增加，流固耦合分析慢慢被重視，國際學者紛紛投入大量資源於研究流固耦合領域。本研究分析流管在橫流(cross flow)內的流場情形，並使用單向流固耦合與雙向流固耦合的方法來比較其結果，分析單向與雙向流固耦合之優缺點，並評估其保守性，最後，將建立的流固耦合分析模式應用於核電廠之組件，例如：殼管式熱交換器，並以三乘三四方排列之模型進行分析，完整評估模擬之安全性與保守性，增加核電廠安全評估的完整性。本篇研究已模擬了單根與雙根圓柱的流固耦合之流沖振動現象，並比較不同的紊流模型之流沖振動現象，選用適合的紊流模型，且已完成模式的校驗確保此分析模式的可行性。在應用方面，也評估了三乘三圓柱陣列之安全性與保守性。

In recent years, the fluid-solid interaction (FSI) is crucial problems in the safety analysis and structure design of industry, for example, steam generators, off shore wind turbines, and submarine communication cables. Vortex-induced vibration is a common problem in the FSI.
In this research, the simulation of a cross flow over single cylinder and two tandem cylinders with one way coupling and two way coupling has been conducted.
The results show the lift and drag coefficient calculated by two way coupling is similar to the results of one way coupling. Different turbulence models for the simulation have been tested too. Furthermore, nine cylinders in square arrangement have been simulated. The result shows that LES model can simulate FIV well at low Reynolds number and cylinders at the downstream should be noted.

摘要 I
Abstract II
目錄 III
圖目錄 V
表目錄 VIII
第一章 緒論 1
1.1 研究背景 1
1.2 文獻回顧 1
1.3 研究目的與流程 4
1.4 分析工具與流程 6
第二章 流固耦合模擬分析 8
2.1 流固耦合現象介紹 8
2.2 統御方程式與紊流模式 11
2.3 單根圓柱模型 16
2.3.1 模型建立 16
2.3.2 網格建立與靈敏度分析 17
2.3.3 邊界條件與紊流模式不準度 18
2.4 兩根圓柱陣列 18
2.4.1 模型建立 18
2.4.2 網格建立與靈敏度分析 19
2.4.3 邊界條件與紊流模式 20
2.5 九根圓柱陣列 21
2.5.1 模型建立 21
2.5.2 網格建立 21
2.5.3 邊界條件與紊流模式 23
第三章 結果與討論 24
3.1 單根圓柱 24
3.2 雙根圓柱 36
3.3 3x3圓柱陣列 41
第四章 結論與建議 50
參考文獻 51

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