本文首先發展在外加垂直震動下強制對流單一沸騰通道分析模式，接著建立反應器爐心以外各組件分析模式，並結合點中子動態模式與燃料棒熱傳導模式，茲以建立在外加垂直震動下進步型沸水式反應器(ABWR)單一沸騰通道自然循環迴路的非線性分析模式。
本研究在加入外部垂直加速度下，探討在外部震盪影響下，系統在不同運轉條件所產生的非線性現象。本文先以非線性分析方法建立系統的穩定性圖譜，再探討系統穩定區域內各穩定點的自然頻率，即共振頻率，之分佈，並據以探討各穩定點的共振效應。本研究分析發現系統穩定區域內之自然頻率數值，落在地震記錄最常被觀測到的震波頻率範圍內，f =0.1 Hz~20Hz，須注意外部地震波對系統安全與穩定運轉之影響。然而，在ABWR的正常運轉點與自然循環點並不會引發劇烈的共振振盪，其是非常穩定的運轉點。此外，當穩定操作點越靠近穩定性邊界時，若加入的外部震盪頻率與當下系統運轉條件之自然頻率相符時，外部震盪導致之共振效應可能造成系統產生不穩定的發散震盪。
本研究亦發展解析及重組實際地震波的方法，可適當模擬真實地震波，並比較真實地震波與模擬地震波對系統所造成之非線性震盪，發現兩者趨勢相當吻合，共振效應會主導其非線性行為。
另一方面，本研究亦進行參數效應之靈敏度分析，結果顯示降低地震對雙相流影響行為的方式有：縮短加熱段管長、增加加熱段管徑、增加進口流阻，降低出口流阻、遠離穩定性邊界及避免共振的發生。

The present study adopts the single nuclear-coupled boiling channel model integrated with external vertical seismic accelerations to investigate the seismic-induced effect on a single nuclear-coupled boiling channel system. Furthermore, a nonlinear model of natural circulation loop in response to the components in ABWR has also been developed for analyzing the effect of seismic accelerations. The nonlinear dynamics and stabilities of a single nuclear-coupled boiling channel and the natural circulation loop are investigated. The void-reactivity feedback would destabilize the system as that reported in the literatures. The natural frequencies of the stable states are widely explored. The results indicate that the natural frequency of initial state could depend on the parameters of phase change number relative to the operating power and subcooling number representing for the condition of inlet subcooling. It tends to increase as the increase in the phase change number or the decrease in the subcooling number. Notably, the system natural frequencies distributed in the stable region are located within the common range of seismic vibration frequency. For the concern of reactor safety, the present study investigates the seismic-induced resonance effect on the nuclear-coupled boiling channel system. The results illustrate that the resonance oscillations could be triggered if the external vibration frequency is the same as the system natural frequency. Moreover, the strength of resonance effect may depend on the inherent stability characteristics of the initial states.
Sensitivity analysis of system parameters, such as length, diameter, inlet/outlet flow resistance, of heated channel, and seismic vibration characteristics have been investigated. The results indicate that the seismic induced oscillations of the single channel system and circulation loop system, in general, could be stabilized by changing several parameters as below:
 Decreasing heated length and outlet flow resistance
 Increasing diameter and inlet flow resistance
 Keep the operating condition (Npch & Nsub) away from the stability boundary

中文摘要 i
英文摘要 iii
誌謝 v
目錄 vii
表目錄 xi
圖目錄 xi
符號系統 xvi
第一章 緒論 1
1.1 前言 1
1.2 研究範圍與目的 1
1.3 論文結構 2
第二章 文獻回顧 3
2.1 雙相流通道穩定性之非線性分析 3
2.2 地震情形下之沸水式反應器工作流體分析 5
2.3 震盪狀態下之雙相流通道實驗 6
2.4 彙整與啟發 7
第三章 模式發展與推導 9
3.1 模式發展結構 9
3.2 地震波模式 10
3.2.1 地震波類型 10
3.2.2 實際案例-美國North Anna核電廠之地震急停事件 12
3.2.3 系統加入外部震盪模式 13
3.3 外加垂直震動下之單一沸騰通道模式[A] 14
3.3.1 前提假設 14
3.3.2 統御方程式 14
3.3.3 模式的建立 15
3.3.4 壓力降 17
3.3.5 地震狀態下強制對流系統壓降之邊界條件 18
3.3.6 外加垂直加速度下入口流速動態 19
3.4 進步行沸水式反應器單一沸騰通道迴路模式 21
3.4.1 上空乏區(Upper Plenum)模式[B] 22
3.4.2 升流管(Riser)模式[C] 23
3.4.3 蒸氣分離器(Steam Separator)模式[D] 24
3.4.4 混合區(Mix Region)模式[E] 25
3.4.5 上降流區(Upper Downcomer)模式[F1] 26
3.4.6 下降流段(Lower Downcomer)模式[F2] 26
3.4.7 下空乏區(Lower Plenum)模式[G] 27
3.4.8 爐心通道單相區模式 28
3.4.9 外加垂直震盪下自然循環迴路爐心通道入口流速動態模式 28
3.5 壓降之摩擦係數 29
3.6 燃料棒熱傳導模式 30
3.7 點中子動態模式 36
第四章 分析方法與模式驗證 38
4.1 重要的無因次參數 38
4.2 特性速度 38
4.3 數值方法 39
4.3.1 穩態解析副程式-SNSQE 39
4.3.2 暫態解析副程式-SDRIV2 40
4.3.3 快速傅立葉轉換-fast Fourier transform 41
4.4 模式驗證 43
第五章 結果與討論 44
5.1 外部垂直加速度對強制對流單一沸騰通道之影響探討 44
5.1.1 穩定性圖譜 44
5.1.2 地震暫態-外部振盪效應 45
5.1.3 靈敏度分析-參數效應 55
5.1.4 實際地震波之解析及應用 62
5.2 外部震盪對簡易型自然循環單一通道迴路之影響 74
5.2.1 穩定性圖譜 74
5.2.2 外部震盪效應 75
5.2.3 靈敏度分析-參數效應 81
5.3 外部震盪對自然循環單一沸騰通道循環迴路之影響 93
5.3.1 穩定性圖譜 93
5.3.2 外部震盪效應 93
5.3.3 靈敏度分析-參數效應 94
第六章 結論與建議 111
6.1 結論 111
6.1.1 強制循環-單一沸騰通道模式 111
6.1.2 自然循環-簡易型單一迴路模式 112
6.1.3 自然循環-單一迴路模式 114
6.2 建議 115
參考文獻 114

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