帳號:guest(216.73.216.88)          離開系統
字體大小: 字級放大   字級縮小   預設字形  

詳目顯示

以作者查詢圖書館館藏以作者查詢臺灣博碩士論文系統以作者查詢全國書目
作者(中文):周彥谷
作者(外文):Chou, Yan-Gu
論文名稱(中文):馬鞍山電廠 MELCOR 2.2 版程式建立與電廠全黑事故分析
論文名稱(外文):Building MELCOR 2.2 Input Deck of Maanshan Nuclear Power Plant and Analyses of Station Blackout Accident
指導教授(中文):馮玉明
指導教授(外文):Ferng, Yuh-Ming
口試委員(中文):王德全
周雄偉
口試委員(外文):Wang, Te-Chuan
Chou, Hsoung-Wei
學位類別:碩士
校院名稱:國立清華大學
系所名稱:工程與系統科學系
學號:107011536
出版年(民國):109
畢業學年度:108
語文別:中文
論文頁數:67
中文關鍵詞:電廠全黑事故MELCOR 2.2
外文關鍵詞:Station Blackout AccidentMELCOR 2.2
相關次數:
  • 推薦推薦:0
  • 點閱點閱:527
  • 評分評分:*****
  • 下載下載:0
  • 收藏收藏:0
本研究利用MELCOR 2.2版程式,進行馬鞍山電廠模式建立與電廠全黑事故之分析,並根據MAAP 5.0.3程式輸入檔進行比對。
本研究透過控制壓力及水位靈敏度的源函數,進行電廠模型的熱水流參數穩態測試,計算時長由負3000秒開始至0秒,結果均在1%的誤差以內。
暫態分析由0秒至30000秒,二次側蒸汽產生器於4313秒燒乾 (Dryout),7715秒燃料裸露 (Core Uncover),燃料間隙於9000秒時拉長 (Gap Release),9347秒時發生誥水反應 (Oxidation),於10514秒時發生燃料遷移 (Relocation),最後於15598秒時反應器壓力槽失效。
MAAP與MELCOR在模擬馬鞍山電廠SBO案例具有相似的熱水流變化趨勢,反應器停機後,衰變熱功率隨即降至7%。二次側蒸汽產生器前期的壓力震盪幅度MAAP小於MELCOR,因MELCOR歷經雙相熱流計算,計算上較難收斂,因此造成較大的震盪,爐心失效時MAAP的壓力變化亦不如MELCOR來得顯著,最後從比對結果顯示,MAAP爐心失效時間略晚於MELCOR; MAAP於肇始事故後隨即流失較多的飼水流量,然而因計算方式的不同,MELCOR後段水位下降速率加快,導致二者在蒸汽產生器燒乾的時間點相近。MAAP的一次側調壓槽壓力於前期受爐心功率下降影響的程度較小,因此壓力下降幅度小於MELCOR;而MAAP的調壓槽水位於爐心失效前便逐漸流失,MELCOR則是隨著爐心的失效而迅速流失。爐心內部水位變化二者相似,氫氣產生量則是MELCOR略高於MAAP。而對爐心失效的預測,MELCOR則相對較MAAP來的保守。
This research used the MELCOR 2.2 to establish the input deck of Maanshan Nuclear Power Plant and analyze the Station Blackout Accident. The results were compared with the input file of MAAP 5.0.3.
In this study, the test of steady state was controlling by several sensitivity studies of mass source or heat source functions. The calculation started from -3000 seconds to 0 seconds, and the results were all within 1% error.
In the transient analysis, the calculation started from 0 seconds to 30000 seconds. The steam generators dried out at 4313 seconds, and the fuel was uncoverd (the water level below TAF) at 7715 seconds. The fuel gap was released at 9000 seconds, oxidation occurred at 9347 seconds, and the relocation occurred at 10514 seconds. Finally, the reactor pressure vessel failed at 15598 seconds.
The comparison showed that these two programs have similar thermal-hydraulic trends. After the reactor shut down, the decay heat power dropped to 7%. Due to the two-phase flow calculationin at the early stage of the accident, it caused a series oscillation of SG pressure in MECLOR. MAAP lost lots of feedwater immediately after the initial event started. However, the times for SG dryout are quite similar in these two programs. And the water lost of pressurizer before the RPV failure was not consistent with the pressure drop in MAAP. While MELCOR seemed more reasonable. For the prediction of RPV failure, MELCOR is relatively conservative than MAAP in simulating the Station Blackout Accident.
摘要 i
ABSTRACT ii
目錄 iii
表目錄 v
圖目錄 vi
第一章 緒論 8
1.1 研究動機與目的 8
1.2 MELCOR程式簡介 9
1.3 SNAP程式簡介 10
1.4 MAAP程式簡介 10
1.5 模擬案例簡介 11
第二章 文獻回顧 12
2.1 電廠設計型態介紹[18] 13
2.2 電廠組件介紹 15
2.3 MELCOR程式輸入檔建立 19
第三章 MELCOR理論模式 31
3.1 MELCOR控制體積與流徑計算 31
3.2 MELCOR爐心熱傳計算 35
3.3 MELCOR爐心幾何設定 38
3.4 MELCOR程式分析流程 42
第四章 電廠全黑案例分析結果 44
4.1 穩態測試 44
4.2 暫態分析 50
4.3 MAAP比對結果 60
第五章 結論 65
參考文獻 66

[1] 陳紹文, "核能系統教材:日本福島核能事故," 2018.
[2] I. Applied Programming Technology, "Symbolic Nuclear Analysis Package (SNAP) User's Manual," March 02, 2020.
[3] B. A. B. L.L. Humphries, F. Gelbard, D.L. Louie, J. Phillips, "MELCOR Computer Code Manuals Vol. 1: Primer and Users’ Guide," November 2018.
[4] I. C.S.Chien & T.C.Wang, "MN-TMBH.INP," September 23, 1998.
[5] 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," 2014.
[6] 核能研究所, "核三廠MAAP5.0.3建立計算書," 2015.
[7] C.-S. C. T.-C. W. Shih-Jen Wang, "Simulation of Maanshan TMLB’ Sequence with MELCOR 1.8.3," April, 1999.
[8] S.-J. W. Te-Chung Wang, and Chun-Sheng Chien, "Analysis of Kuosheng Large-Break Loss-Of-Coolant Accident with MELCOR 1.8.4," September, 2000.
[9] 張. 靖, "馬鞍山電廠MELCOR2.1模式建立與嚴重事故分析," 2017.
[10] J.-R. W. Yu Chiang, Ai-Ling Ho, Wen-Sheng Hsu, Jyh-Tong Teng, Jing Chang and Shao-Wen Chen and Chunkuan Shih, "Extended Loss of AC Power (ELAP) Analysis of Kuosheng BWR/6 Using MELCOR2.1/SNAP," 2016.
[11] 蔣宇、王仲容、陳紹文、施純寬, "MELCOR2.1/SNAP程式於馬鞍山電廠全黑事故之氫氣行為評估及動畫設計," 2017.
[12] J. M. M.-V. F. Martin-Fuertes, J. Mira, M.J. Sanchez, "A MELCOR Application to Two Light Water Reactor Nuclear Power Plant Core Melt Scenarios with Assumed Cavity Flooding Action," October, 2003.
[13] R. O. Gauntt, "Uncertainty Analyses Using the MELCOR Severe Accident Analysis Code," 2007.
[14] M. J. W. L.Z Li, W.X. Tian, G.H. Su, S.H. Qiu, "Severe accident analysis for a typical PWR using the MELCOR code," 2014.
[15] Y. P. Z. J. Wang, K.Y. Mao, Y.J. Huang, S.Z. Qiu, "MELCOR simulation of core thermal response during a station blackout initiated severe accident in China pressurized reactor (CPR1000)," 2015.
[16] J. H. K. J.M. Yoo, B.J. Yun, S.W. Hong, J.J. Jeong, "Improvement of the MELCOR condensation heat transfer model for the thermal-hydraulic analysis of a PWR containment," 2018.
[17] A. R. L. Fernandez-Moguel, T. Lind, "Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: Thermal-hydraulic analysis," 2019.
[18] 苑穎瑞, "高等熱流學教材:壓水式電廠系統介紹," 2019.
[19] 台灣電力公司, "核能電廠訓練教材:蒸汽產生器," 2008.
[20] B. A. B. L.L. Humphries, C. Faucett, F. Gelbard, T. Haskin, D.L. Louie, J. Phillips, "MELCOR Computer Code Manuals Vol. 2: Reference Manual," November 2018
[21] J. J. Larry L. Humphries, R. Gauntt (SNL) and Hossein Esmaili (NRC), "Input Deck Conversion (1.8.5 to 1.8.6 and 1.8.6 to 2.1)."
 
 
 
 
第一頁 上一頁 下一頁 最後一頁 top
* *