在日本福島事故之後，各界對於此複合式災難對電廠的衝擊產生不少疑慮，台灣電力公司便針對各電廠提出斷然處置措施，以期在此超過設計基準事故的災難發生時，能確保反應爐爐心不會毀損。本論文利用熱水流分析程式─TRACE所建立之龍門電廠TRACE模式，分析針對龍門電廠所提出之斷然處置措施。其結果顯示，在有進行斷然處置措施的情況之下，可讓護套溫度保持在法規限值1088 K以下。然而，在現行的龍門TRACE模式中，並未實際模擬圍阻體組件，如此一來，對於斷然處置措施的討論便有其侷限性，故本論文也利用圍阻體模擬程式─CONTAN，建立龍門TRACE/CONTAN模式，並利用輸入FSAR邊界條件以及直接利用爐心計算其熱水流條件兩種方式來模擬主蒸汽管斷裂事故。在輸入FSAR邊界條件的案例中，龍門CONTAN模式與FSAR及GOTHIC程式所模擬之結果趨於一致。而在爐心計算的案例中，上乾井溫度在一開始計算出偏高的數值後，再慢慢降回至與其他兩程式相同的平衡溫度，若由真實情況來觀察此結果，可發現其經歷了一段能量平衡的過程，此為其他兩程式所看不到之現象，故雖然龍門TRACE/CONTAN模式所計算之乾井溫度偏高，但卻為較貼近實際情況之結果。

All walks of life are doubtful about the safety of nuclear power plant after the Fukushima accident. As a result, the Taipower company applies Ultimate Response Guideline(URG) to all nuclear power plants in Taiwan in a hope that reactor core damage won’t happen when any beyond design basis accident occurs. This essay uses Lumgmen TRACE model to investigate whether the URG is helpful or not to Lungmen NPP. The results reveal that cladding temperature can keep under the limit(1088 K) when URG is followed.
This essay also establish an improved Lungmen TRACE/CONTAN model by containment analysis code─CONTAN. It utilizes FSAR boundary condition as well as calculates its thermal hydraulic boundary directly by TRACE to perform the main steam line break event. In a case study of FSAR boundary condition, the result of Lungmen CONTAN model coincides with that of FSAR and GOTHIC. In another case study of reactor core calculation, it has a higher temperature in the beginning and gradually decline which meets the same balance temperature of the other two codes’ results. By observing the real phenomenon, it is clear that it has experienced an energy balance process, which can’t be found in those two codes’ results. By the above-mentioned results, we can conclude that Lungmen TRACE/CONTAN model is more practical though it has a relatively high drywell temperature.

目錄
摘要 i
ABSTRACT ii
致謝 iii
表目錄 vii
圖目錄 viii
符號表 xi
縮寫表 xii
第一章 緒論 1
1.1 研究動機 1
1.2 研究架構 2
第二章 文獻回顧 3
2.1 龍門TRACE模式相關研究 3
2.2 斷然處置相關研究 3
2.3 圍阻體相關研究 4
第三章 程式介紹 5
3.1 SNAP介面介紹 5
3.2 TRACE程式介紹 8
3.2.1 壓力槽組件(VESSEL) 8
3.2.2 通道組件(CHEN) 8
3.2.3 管路組件(PIPE) 9
3.2.4 閥組件（VALVE） 9
3.2.5 破口組件(BREAK) 10
3.2.6 注水組件(FILL) 10
3.3 CONTAN程式介紹 12
3.3.1 控制體積組件(COMPARTMENT) 12
3.3.2 被動接結組件(PASSIVE JUNCTION) 13
3.3.3 熱結構組件(HEAT STRUCTURE) 15
第四章 龍門TRACE/CONTAN模式建立 19
4.1 龍門電廠TRACE模式 19
4.1.1 反應爐壓力槽設定 19
4.1.2 反應爐爐心設定 20
4.1.3 主蒸汽管路設定 20
4.1.4 爐內泵設定 21
4.1.5 飼水管路設定 21
4.1.6 緊急爐心冷卻系統設定 21
4.2 龍門電廠CONTAN模式 30
4.2.1 龍門RCCV構造 30
4.2.2 龍門CONTAN模式 31
4.2.2.1 上乾井 31
4.2.2.2 下乾井 32
4.2.2.3 乾井連接通道 32
4.2.2.4 水平連接通道 33
4.2.2.5 濕井 33
4.3 TRACE/CONTAN耦合 34
第五章 龍門電廠案例分析 39
5.1 主蒸汽管斷裂事件 39
5.1.1 FSAR邊界條件 41
5.1.1.1 事件描述 41
5.1.1.2 邊界條件 41
5.1.1.3 結果比較 42
5.1.2 爐心計算 52
5.1.2.1 邊界條件 52
5.1.2.2 結果比較 53
5.2 斷然處置分析 61
5.2.1 事件描述及假設 62
5.2.2 TRACE結果分析 66
5.2.3 TRACE與RELAP5結果比較 73
第六章 結論與建議 78
6.1 結論 78
6.2 建議 81
參考文獻 83
附錄A 85

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[16] TRACE V5.0 USER’S MANUAL, Volume 2：Modeling Guidelines, U.S. Nuclear Regulatory Commission