TRACE是一個強而有力的核電廠安全分析程式，目前的金山核電廠TRACE模式，經驗證後已可應用於相當多的安全分析上，但是主要都是在爐心熱流的安全分析。因此，本論文的研究方向是將目前金山核電廠TRACE模式分析計算發展至下游的圍阻體系統分析及上游的中子動力學計算。
下游方向發展至圍阻體分析方面，發展金山核電廠TRACE/CONTAN模式，將爐心熱流分析的TRACE結合圍阻體分析的組件CONTAN，以進行爐心熱流及圍阻體系統同步計算分析。本研究已應用TRACE/CONTAN模式進行LOCA、SBO 24小時及URG的分析。其中LOCA事故分析顯示TRACE/CONTAN模式與FSAR及GOTHIC程式分析結果比較，可以獲得令人滿意的分析結果。SBO 24小時事故分析顯示，比較TRACE/CONTAN模式與RETRAN-02加上SHEX的分析結果，兩者也十分吻合。金山核電廠的TRACE/CONTAN模式進行URG分析的結果顯示，URG的兩階段降壓策略，較直接作緊急降壓，可更有效降低事故過程的燃料護套尖峰溫度，所需的最小替代注水量也遠低於直接作緊急降壓。
上游方向拓展至中子動力學計算方面，發展金山核電廠TRACE/PARCS模式，將爐心熱流分析的TRACE結合反應爐爐心模擬器PARCS，以進行爐心熱流及爐心中子熱力學同步計算分析，本研究已利用電廠啟動測試資料的暫態案例，進行金山核電廠TRACE/PARCS模式的驗證，驗證分析包括六項啟動測試暫態分析，模擬結果顯示TRACE/PARCS模式可以良好的分析金山核電廠的啟動測試暫態，並且具備一定的準確度。金山核電廠TRACE/PARCS模式進一步應用於控制棒擾動穩定性模擬上，由模擬的結果可明顯的觀察到功率以及燃料組件內流量的震盪，並驗證爐心系統的穩定性。

TRACE is a thermal-hydraulic analysis code for reactor safety. The current Chinshan NPP TRACE model has been verified and can be applied to safety analysis for the reactor coolant system. Therefore, this research attempts to extend the applications of the Chinshan NPP TRACE model to the containment system analysis and the neutron kinetic calculation.
The downstream direction is extended to the analysis of the containment system, so the TRACE/CONTAN model of Chinshan NPP was developed. The TRACE, a reactor coolant system analysis code, was combined with the CONTAN, a special module for the containment system analysis, to perform the real-time calculation. In this study, the TRACE/CONTAN model has been used to analyze LOCA, SBO 24 hours, and URG. The result of LOCA accident analysis shows that the TRACE/CONTAN mode can obtain satisfactory analysis results. The result of the SBO 24 hours accident analysis showed that comparing the TRACE/CONTAN with the analysis results of RETRAN/SHEX is also very consistent. The results of URG analysis in the TRACE/CONTAN model of Chinshan NPP show that URG’s two-stage depressurization strategy is safer than one-stage emergency depressurization, which can more effectively reduce the peak temperature of the fuel cladding during the accident and the minimum requirement of alternative water injection.
The upstream direction is extended to the calculation of neutron kinetics, the TRACE/PARCS model of Chinshan NPP is developed, and the TRACE of the reactor coolant system analysis is combined with the reactor core simulator PARCS to perform real-time calculation and analysis of the reactor coolant system and the neutron kinetics of the reactor core. This study has used the transient case of power plant start-up test data to verify the TRACE/PARCS model of Chinshan NPP. The verification analysis includes six transient analyses of start-up tests. The simulation results show that the TRACE/PARCS model can well analyze the transients of start-up test in Chinshan NPP’s, and achieve a certain degree of accuracy. The TRACE/PARCS model of Chinshan Nuclear Power Plant is further applied to the simulation of control rod perturbance stability. In the results of the simulation, the oscillation of power and flow in the fuel assembly can be observed, and the stability of core system could be approved.

中文摘要 i
英文摘要 iii
誌 謝 v
目 錄 vii
附表目錄 xi
附圖目錄 xiii
專有名詞 xxi
第一章 前言 1
第二章 文獻回顧 5
第三章 金山核電廠簡介 11
3.1 反應爐壓力槽 11
3.2 再循環管路系統 12
3.3 汽水分離器與蒸汽乾燥器 13
3.4 爐心燃料 14
3.5 主蒸汽供給系統 14
3.6 緊急爐心冷卻系統 15
3.7 圍阻體 15
第四章 分析程式簡介 27
4.1 圖形化使用者介面程式SNAP簡介 27
4.2 熱水流分析程式TRACE簡介 31
4.2.1 反應爐壓力槽組件VESSEL簡介 32
4.2.2 核子燃料組件CHAN簡介 34
4.2.3 圍阻體組件CONTAN簡介 37
4.2.4 統御方程式及重要熱水流現象 39
4.3 爐心模擬程式PARCS簡介 54
第五章 金山核電廠TRACE及PARCS模式建置與穩態分析 59
5.1 資料蒐集及分類 59
5.1.1 熱水流幾何資料 59
5.1.2 反應爐壓力槽和內部組件資料 60
5.1.3 熱結構資料 61
5.1.4 控制系統資料 62
5.1.5 初始條件和邊界條件資料 63
5.2 模式建立步驟 64
5.2.1 定義組件 64
5.2.2 建置網格節點 65
5.2.3 摩擦損失 66
5.2.4 重要熱水流現象設定 66
5.2.5 註解與ID編碼 66
5.2.6 模式除錯 67
5.3 金山核電廠TRACE模式的建立 68
5.3.1 反應爐壓力槽 68
5.3.2 再循環系統 69
5.3.3 汽水分離器與蒸汽乾燥器 69
5.3.4 爐心燃料 70
5.3.5 蒸汽供應系統 70
5.3.6 閥門 71
5.3.7 控制系統 71
5.3.8 爐心功率(中子動力源) 72
5.3.9 金山核電廠圍阻體模式的建立 72
5.3.10 反應爐冷卻水系統與圍阻體系統的整合 73
5.4 金山核電廠PARCS模式的建立 84
5.4.1 金山核電廠反應爐爐心PARCS模式的建立 84
5.4.2 金山核電廠TRACE/PARCS模式的耦合 85
5.5 金山核電廠TRACE與PARCS模式的穩態計算 92
5.5.1 TRACE模式穩態分析 92
5.5.2 TRACE/CONTAN模式穩態分析 92
5.5.3 TRACE/PARCS模式的穩態分析 93
第六章 金山核電廠TRACE圍阻體模式相關分析 101
6.1 喪失冷卻水事件暫態響應分析 101
6.1.1 喪失冷卻水事件分析概述 101
6.1.2 喪失冷卻水事件 104
6.1.3 結果與討論 108
6.2 金山核電廠24小時電廠全黑承受能力之評估 132
6.2.1 SBO 24小時承受能力評估概述 132
6.2.2 SBO 24小時TRACE/CONTAN模式分析 136
6.2.3 結果討論 140
6.3 金山核電廠斷然處置措施分析 152
6.3.1 斷然處置措施制定概述 152
6.3.2 TRACE/CONTAN分析URG 156
6.3.3 結果討論 160
第七章 金山核電廠TRACE/PARCS模式相關分析 171
7.1 金山核電廠TRACE/PARCS模式的啟動測試暫態分析 171
7.1.1 啟動測試暫態分析概述 171
7.1.2 100%功率負載棄載測試 175
7.1.3 83%功率汽機跳脫測試 183
7.1.4 84%功率主蒸汽隔離閥關閉測試 189
7.1.5 97%功率再循環泵跳脫測試 195
7.1.6 83%功率喪失飼水加熱測試 200
7.1.7 98%功率飼水泵跳脫測試 205
7.1.8 100%功率負載棄載測試時反應爐急停速度的敏感度研究 212
7.1.9 再循環流量相關的反應度變化 217
7.1.10 結果討論 227
7.2 金山核電廠控制棒擾動穩定性模擬 228
7.2.1 沸水式反應爐穩定性特性 228
7.2.2 暫態描述 230
7.2.3 模式設定 231
7.2.4 結果討論 232
第八章 結論與建議 253
8.1 結論 253
8.2 建議 259
參考文獻 261

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