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作者(中文):陳偉懋
作者(外文):Chen, Wei-Mao
論文名稱(中文):MELCOR潛變破裂研究分析與國際間SAMG嚴重事故管理指引探討
論文名稱(外文):Analysis of Creep Rupture with MELCOR and Discussion on International Severe Accident Management Guidelines
指導教授(中文):陳紹文
王仲容
指導教授(外文):Chen, Shao-Wen
Wang, Jong-Rong
口試委員(中文):鄭憶湘
楊融華
口試委員(外文):Cheng, I-Hsiang
Yang, Jung-Hua
學位類別:碩士
校院名稱:國立清華大學
系所名稱:核子工程與科學研究所
學號:109013517
出版年(民國):111
畢業學年度:110
語文別:中文
論文頁數:105
中文關鍵詞:電廠全黑自然循環潛變破裂MELCOR2.2SAMG
外文關鍵詞:Station BlackoutNatural CirculationCreep RuptureMELCOR2.2SAMG
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本研究精進了MELCOR馬鞍山電廠模型,並將使用版本更新至最新的2.2版,在衰變熱、爐心燃料等地方都比之前更為貼近現實結果,且也與FSAR(Final Safety Analysis Report)等資料進行穩態比對,驗證其準確性。為了觀察管路潛變破裂的狀況,本模擬假設為極端狀況,在電廠發生STSBO(Short-Term Station Blackout)且蒸汽驅動輔助飼水系統失效情境下之管路潛變破裂模擬。模擬結果顯示,電廠在發生全黑事故後約1.7小時蒸汽產生器水蒸乾、7.7小時爐心水位降至TAF(Top of Active Fuel)、約8.9小時爐心同時達到燃料護套鋯水反應溫度與進入SAMG(Severe Accident Management Giudeline)條件溫度,最後在9.7小時出現熱端管路潛變破裂現象,而在熱端管路發生潛變破裂的同時,蒸汽產生器U型管並未有潛變破裂的跡象,此結果與國外文獻一致;而根據文獻,RPV(Reactor Pressure Vessel)失效的時間必定比管路發生潛變破裂的時間來的晚發生。
另外,有鑑於國內對於管路潛變破裂事故後的緩和策略研究並不多,故本研究在成功模擬馬鞍山電廠全黑事故後,又根據國際間文獻蒐集與統整,進行了嚴重事故管理指引SAMG模擬。在考量馬鞍山電廠的狀況後,本研究選擇在進入SAMG後,立即開啟1個以上的PORV(Pilot Operated Relief Valve)做為模擬措施,而模擬結果顯示,若馬鞍山電廠在達到進入SAMG條件後開啟2個以上PORV即可有效延後熱端管路潛變破裂與RPV失效的時間,有助於SAMG執行。

關鍵字:電廠全黑、潛變破裂、MELCOR 2.2、SAMG
The MELCOR model of Maanshan nuclear power plant has been improved and updated to the latest version (ver. 2.2) in this research. Comparing to MELCORE 2.1, the calculation by using MELCORE 2.2 in decay heat and core fuel is closer to the reality. Also, the steady-state model is verified by comparing the results of FSAR and Maanshan training materials.
After completing the Maanshan MELCOR model, this research uses the initial condition from SOARCA project to analyze whether Maanshan nuclear power plant will occur pipe creep rupture. The result of simulation shows that steam generator will dry out after 1.7 hours and the water level in core will drop down to TAF after 7.7 hours. Fuel cladding temperature will reach 1088.7 K after around 8.9 hours,, and the hot leg creep rupture will occur after 9.7 hours.
Due to lack of research about creep rupture mitigation strategy, this study simulates the consequences of Maanshan nuclear power plant under SBO accident. So as to develope its SAMG. We consider the PORV effect on mitigation strategy. The simulation results show that there are no positive effects on mitigation when only one set of PORV is open. Only if more than two sets of PORVs are open, the occurrence of hot leg creep rupture and RPV failure can be mitigated effectively.

Keywords:Station Blackout (SBO), Creep Rupture, MELCOR 2.2, SAMG
摘要 i
Abstract ii
致謝 iii
目錄 iv
表目錄 vi
圖目錄 vii
符號表 x
第一章 緒論 1
1.1 研究動機與方法論 1
1.2 論文架構 3
第二章 文獻回顧 5
2.1 潛變破裂與緩和策略文獻回顧 5
2.2 文獻彙整 19
第三章 模擬程式與電廠介紹 34
3.1 MELCOR程式介紹 34
3.2 馬鞍山電廠模式介紹 35
3.2.1 馬鞍山電廠模式基本設定 36
3.2.2 COR模組介紹 37
3.3 衰變熱設定 42
3.4 穩態模擬結果 43
3.5 SNAP圖形化介面程式 43
第四章 馬鞍山電廠全黑事故與管路潛變破裂模擬 71
4.1 馬鞍山電廠MELCOR模式建立 71
4.2 潛變破裂模擬說明 71
4.2.1 潛變破裂模擬設定方法 72
4.2.2 潛變破裂邏輯設定組件 74
4.3 馬鞍山電廠全黑事故假設與初始條件 74
4.3.1 馬鞍山電廠全黑事故模擬方法 75
4.4 馬鞍山電廠全黑事故下管路潛變破裂模擬結果 75
4.5 馬鞍山電廠潛變破裂模擬結果動畫模式 77
第五章 潛變破裂現象的防範及嚴重事故管理指引影響模擬 89
5.1 國內外嚴重事故管理指引方向 89
5.2 蓄壓槽注水組件建立 89
5.3 嚴重事故管理指引之影響模擬 89
5.4 小結 91
第六章 結論與未來建議 99
6.1 結論 99
6.2 未來建議 100
參考文獻 102

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