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研究生:陳偉懋
研究生(外文):Chen, Wei-Mao
論文名稱: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:陳紹文陳紹文引用關係王仲容
指導教授(外文):Chen, Shao-WenWang, Jong-Rong
口試委員:鄭憶湘楊融華
口試委員(外文):Cheng, I-HsiangYang, Jung-Hua
口試日期:2022-07-21
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
學門:工程學門
學類:核子工程學類
論文種類:學術論文
論文出版年:2022
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
[1] P. Gauntt, D.K., Jeff Cardoni, Jesse Phillips, Andrew Goldmann, Susan Pickering, Matthew Francis, Kevin Robb, Larry Ott, Dean Wang, Curtis Smith, Shawn St.Germain, David Schwieder, Cherie Phelan, “Fukushima Daiichi Accident Study (Status as of April 2012)”, Sandia National Lab, 2012
[2] SandiaNL, “State-of-the-Art Reactor Consequence Analysis Project Volume 2: Surry Integrated Analysis”, NUREG/CR-7110, 2012.
[3] Sergey Galushin, Pavel Kudinov, “Sensitivity Analysis of the Vessel Lower Head Failure in Nordic BWR using MELCOR Code”, PSAM14, 2018.
[4] S.A. Chavez, J.L. Rempe, “Finite Element Analysis of a BWR Vessel and Penetration under Severe Accident Conditions”, Nuclear Engineering and Design, 1994, p. 413-435.
[5] 陳詩奎、陳得誠、林子仁等人, “核三廠電廠全黑事故序列驗證評估”, 行政院原子能委員會核能研究所委託計畫研究報告, 2016.
[6] Yoshihito Yamaguchi, Jinya Katsuyama, Yoshiyuki Nemoto, Yoshiyuki Kaji, Hiroyuji Yoshida, Yinsheng Li, “Development of Failure Evaluation Method for BWR Lower Head in Severe Accident; High Temperature Creep Test and Creep Damage Model”, Mechanical Engineering Journal, 2017.
[7] Y. Liao, K. Vierow, “MELCOR Analysis of Steam Generator Tube Creep Rupture in Station Blackout Severe Accident”, Nuclear Technology, 2005.
[8] CHEN Bao-wen, MAO Huan, Xiang-cheng, and CHEN Bin, “Risk Analysis for Steam Generator Tube Creep Rupture Under Severe Accident Induced by Station Blackout”, Atomic Energy Science and Technology, 2014.
[9] Youngsuk Bang, Gunhyo Jung, Byungchul Lee, and Kwang-Il Ahn, “Estimation of temperature induced reactor coolant system and steam generator tube creep rupture probability under high pressure severe accident”, Journal of Nuclear Science and Technology, 2012.
[10] JinHo Song, ByungHee Lee, SungIl Kim, and Gwang Soon Ha, “An Analysis on the Consequences of a Severe Accident Initiated Steam Generator Tube Rupture”, Nuclear Engineering and Design, 2019.
[11] Deng Jian, Cao Xuewu, “Analysis of hot leg natural circulation under station blackout severe accident”, Nuclear Science and Techniques, 2007.
[12] J. Husarcek, L. Kubisova, S. Capekova, “Status Report on UJD Activities in the Field of Severe Accidents”, CSARP/MCAP, 2021.
[13] T. Van Rompuy, R. Thomas, A. Malkhasyan, D. Gryffroy, “RECENT SEVERE ACCIDENT ACTIVITIES IN BELGIUM”, CSARP/MCAP, 2021.
[14] Te-Chuan Wang, S. J. Wang, “Analysis of BWR Large Break LOCA with MELCOR 1.8.5”, Institute of Nuclear Energy Research, 2005.
[15] 李煒婷, “使用MELCOR程式模擬福島一場三號機事故與放射性物質外釋量之分析”, 國立清華大學碩士論文, 2014.
[16] 張賀嵎, “核三廠MELCOR程式輸入檔的建立與電廠全黑嚴重事故分析”, 國立清華大學碩士論文, 2014.
[17] 張靖, “馬鞍山電廠MELCOR2.1模式建立與嚴重事故分析”, 國立清華大學碩士論文, 2017.
[18] 蔣宇, “MELCOR2.2程式與沸水式反應器嚴重事故分析之模式建立與應用”, 國立清華大學碩士論文, 2018.
[19] Zhang Long Fei, Zhang Da Fa, Xu Jin Liang, “Station Blackout Accident and Mitigation Measure for PWR-NPP”, Atomic Energy Science and Technology, 2008.
[20] L. Wu, H. Miao, P. Yu, Z. Huang, “Study of PWR hot leg creep rupture and RCS depressurization strategy during an SBO accident”, Kerntechnik, 2021.
[21] Kwang-Il Ahn, Soo-Yong Park, Wonjun Choi, Sung Joong Kim, “Best-practice severe accident analysis for the OPR1000 short-term SBO sequence using MELCOR2.2 and MAAP5”, Annals of Nuclear Energy, 2021.
[22] Wonjun Choi, Sung Joong Kim, “MELCOR simulation of in-vessel mitigation strategies by multiple actions using monte carlo method”, Transactions of the Korean Nuclear Society Virtual Spring Meeting, 2020.
[23] Ga-eul Choi, Kwang-Il Ahn, Keo-hyoung lee, Su-won lee, Seok-Won Hwang, “Plant-specific assessment of the natural circulation-induced creep rupture characteristics in the RCS pressure boundary during the SBO accident”, Progress in Nuclear Energy, 2021.
[24] Jaehyun Cho, Samg Hun lee, Jaewhan Kim, Seong Kyu Park, “Framework to model severe accident management guidelines into Level 2 probabilistic safety assessment of a nuclear power plant”, Reliability Engineering & System Safety, 2022.
[25] SAND2017-5599, "QUICKLOOK OVERVIEW OF MODEL CHANGES IN MELCOR 2.2: Rev 6342 to Rev 9496", Sandia National Laboratories, 2017.
[26] 鄭惟遠, “馬鞍山電廠MELCOR2.2模式全黑事故結合熱端管路潛變破裂事故分析”, 國立清華大學碩士論文, 2019.
[27] 台灣電力公司第三核能發電廠, “Phase II PWRT訓練教材”, 2006.
[28] 台灣電力公司第三核能發電廠, “終期安全分析報告(FSAR) ”, 1994。
[29] Sandia National Lab, “MELCOR Computer Code Manuals Vo2.: Reference Manual, Version 2.2.9541”, Sandia National Laboratory, 2017.
[30] American Nuclear Society Standards Committee Working Group ANS-5.1, “American National Standard for Decay Heat Power in Light Water Reactor”, American Nuclear Society, 1979.
[31] L.L. Humphries, B.A. Beeny, F. Gelbard, D.L. Louie, J. Phillips, “MELCOR Computer Code Manuals Vol. 2: Reference Manual”, Sandia National Laboratories, January 2017.
[32] 陳紹文、楊融華、王仲容、陳詩奎、陳得誠、陳偉懋、張鴻均、陳雄智、陳韶萱、陳玄哲、江秉修, “壓水式核能電廠於電廠全黑事故下防範潛變破裂及緩和策略研究分析”, 科技部專題研究計畫結案報告, 2022.
[33] 陳偉懋、蔣宇、王仲容、楊融華、陳紹文, “模擬核三廠於電廠全黑事故下潛變破裂及緩和策略研究分析”, 中國機械工程學會第38屆全國學術研討會, 2021
[34] Sandia National Lab, “MELCOR Computer Code Manuals Vol.3: MELCOR Assessment Problems, Version 2.1.7347”, Sandia National Laboratory, 2015.
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