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完整後設資料紀錄
DC 欄位 | 值 | 語言 |
---|---|---|
dc.contributor.advisor | 黃尹男(Yin-Nan Huang) | |
dc.contributor.author | Ching-Ching Yu | en |
dc.contributor.author | 游青青 | zh_TW |
dc.date.accessioned | 2021-05-15T17:52:16Z | - |
dc.date.available | 2019-08-16 | |
dc.date.available | 2021-05-15T17:52:16Z | - |
dc.date.copyright | 2014-08-16 | |
dc.date.issued | 2014 | |
dc.date.submitted | 2014-08-12 | |
dc.identifier.citation | Applied Technology Council (ATC). (2012). 'Seismic performance assessment of buildings. Volume 1 – Methodology.' FEMA P-58 pre-release version, Federal Emergency Management Agency. Washington, D.C.
Apsel, R., and Luco, J. (1987). 'Impedance functions for foundations embedded in a layered medium: an integral equation approach.' Earthquake engineering & structural Dynamics, 15(2), 213-231. American Society of Mechanical Engineers (ASME) and American Nuclear Society (ANS). (2009). “Standard for Level 1 - large early release frequency probabilistic risk assessment for nuclear power plant applications.” ASME-ANS RA-Sa-2009, Addendum A to RA-S-2008, New York, NY. American Society of Civil Engineers (ASCE). (2012). “Seismic analysis of safety-related nuclear structures.” ASCE 4-09, Reston, Virginia. (to be published) Baker, J. W., and Cornell, C. A. (2006). 'Correlation of response spectral values for multicomponent ground motions.' Bulletin of the Seismological Society of America, 96(1), 215-227. Budnitz, R. J., Amico, P. J., Cornell, C. A., Hall, W. J., Kennedy, R. P., Reed, J. W., and Shinozuka, M. (1985). “An approach to the quantification of seismic margins in nuclear power plants.” NUREG/CR-4334, U.S. Nuclear Regulatory Commission, Washington, D.C. Bu Seog Ju, and Woo Young Jung. (2013). ” Evaluation of Performance Requirements for Seismic Design of Piping System.” World Academy of Science, Engineering and Technology International Journal of Civil, Architectural, Structural, Urban Science and Engineering Vol:7 No:2 Computers and Structures, Inc. (CSI) (2006). SAP2000 Linear and Nonlinear Static and Dynamic Analysis and Design of Three-Dimensional Structures-version 11.0. Computers and Structures, Inc., Berkeley, California. Chen, J. T., Chokshi, N. C., Kenneally, R. M., Kelly, G. B., Beckner, W. D., McCracken, C., Murphy, A. J., Reiter, L., and Jeng, D. (1991). “Procedural and submittal guidance of individual plant examination of external events (IPEEE) for severe accident vulnerabilities.” NUREG-1407, U.S. Nuclear Regulatory Commission, Washington, D.C. Campbell, R., Hardy, G., and Merz, K. (2002). “Seismic fragility application guide.” TR-1002988, Electric Power Research Institute, Palo Alto, CA. Engineers, A. s. o. c. (2007). Seismic rehabilitation of existing buildings, ASCE Publications. Huang, Y.-N., Whittaker, A. S., Kennedy, R. P., and Mayes, R. L. (2009). “Assessment of base-isolated nuclear structures for design and beyond-design basis earthquake shaking.” MCEER-09-0008, Multidisciplinary Center for Earthquake Engineering Research, State University of New York, Buffalo, NY. Huang, Y.-N., Whittaker, A. S., and Luco, N. (2011a). “A probabilistic seismic risk assessment procedure for nuclear power plants: (I) Methodology.” Nuclear Engineering and Design, 241(9), 3996-4003 Huang, Y.-N., Whittaker, A. S., and Luco, N. (2011b). “A probabilistic seismic risk assessment procedure for nuclear power plants: (II) Application.” Nuclear Engineering and Design, 241(9), 3985-3995 I.M. Idriss, and J.I. Sun. (1992). SHAKE, A Computer Program for Conducting Equivalent Linear Seismic Response Analyses of Horizontally Layered Soil Deposits, University of California, Davis Jayaram, N., Lin, T., and Baker, J. W. (2011). 'A Computationally efficient ground-motion selection algorithm for matching a target response spectrum mean and variance.' Earthquake Spectra, 27(3), 797-815. Kennedy, R., Hardy, G., Merz, K. (2009). “Seismic fragility application guide update.” TR-1019200, Electric Power Research Institute, Palo Alto, CA. Md Shahin Reza, Oreste S. Bursi, Giuseppe Abbiati, Alessio Bonelli. (2013). ” Pseudo-dynamic Heterogeneous Test With Dynamic Substructuring of A Piping System Under Earthquake Loading.” Proceedings of the ASME 2013 Pressure Vessels and Piping Conference, Paris, France. Norme Techniche. (2008). “Norme Techniche per le costruzioni,” DM Infrastrutture, 14 gennaio 2008. Pacific Earthquake Engineering Research Center (PEER). (2011). 'PEER Ground Motion Database.' http://peer.berkeley.edu/peer_ground_motion_database Pickard, Lowe, and Garrick, Inc., and Westinghouse Electric Corporation, Fauske & Associates, Inc. (1981). “Zion Probabilistic Safety Study.” prepared for Commonwealth Edison Company, Chicago. Prassinos, P. G., Ravindra, M. K., and Savy, J. B. (1986). “Recommendations to the Nuclear Regulatory Commission on trial guidelines for seismic margin reviews of nuclear power plants.” NUREG/CR-4482, U.S. Nuclear Regulatory Commission, Washington, D.C. Reed, J. W., Kennedy, R. P., Buttemer, D. R., Idriss, I. M., Moore, D. P., Barr, T., Wooten, K. D., and Smith, J. E. (1991). “A methodology for assessment of nuclear power plant seismic margin.” EPRI-NP-6041-M-Rev.1, Electric Power Research Institute, Palo Alto, CA. Reed, J. W., and Kennedy, R. P. (1994). “Methodology for developing seismic fragilities.” TR-103959, Electric Power Research Institute, Palo Alto, CA. Ronald E. Walpole, Raymond H. Myers, Sharon L. Myers, Keying Ye. (2007). “Probability and Statistics for Engineers and Scientists.” Pearson Education International Smith, P. D., Dong, R. G., Bernreuter, D. L., Bohn, M. P., Chuang, T. Y., Cummings, G. E., Johnson, J. J., Mensing, R. W., and Wells, J. E. (1981). “Seismic safety margins research program: phase 1 final report.” NUREG/CR-2015, U.S. Nuclear Regulatory Commission, Washington, D.C. S. Vishnuvardhan, P. Gandhi, G. Raghava, M. Saravanan, DM. Pukazhendhi, Sumit Goyal, Sunil Satpute, Suneel K. Gupta, Vivek Bhasin, and K. K. Vaze. (2011). “Quasi-Cyclic Fracture Studies On Narrow Gap Welded Stainless Steel Straight Pipes.” Transactions, SMiRT 21, New Delhi, India. U.S. Nuclear Regulatory Commission (USNRC). (1975). “Reactor safety study.” WASH-1400, NUREG-73/041. U.S. Nuclear Regulatory Commission (USNRC). (1983). “PRA procedures guide.” NUREG/CR-2300, USNRC, Washington, D.C. U.S. Nuclear Regulatory Commission (USNRC). (1991). “Individual plant examination of external events (IPEEE) for severe accident vulnerabilities.” Generic Letter No. 88-20, Supplement 4, USNRC, Washington, D.C. U.S. Nuclear Regulatory Commission (USNRC). (2010). “Analysis of JNES Seismic Tests on Degraded Piping.” NUREG/CR-7015, USNRC, Washington, D.C. Wood, S. L. (1990). 'Shear strength of low-rise reinforced concrete walls.' ACI Structural Journal, 87(1). Yang, T.Y., Moehle, J., Stojadinovic, B., and Der Kiureghian, A. 2009. Performance evaluation of structural systems: theory and implementation. Journal of Structural Engineering 135 (10), 1146–1154. | |
dc.identifier.uri | http://tdr.lib.ntu.edu.tw/jspui/handle/123456789/5126 | - |
dc.description.abstract | 2011 年,Huang 與Whittaker 等人提出了一套新的地震機率式風險評估(Seismic Probabilistic Risk Assessment, SPRA)方法,此法改進現今習用方法之缺點,具有以下特點:1) 採取以結構反應參數為函數之地震易損性曲線;2)使用非線性動力分析決定元件耐震需求;3)採用統計方法增廣反應歷時分析結果的數量;4)使用蒙地卡羅模擬識別元件失效與否。在Huang 與Whittaker 等人提出之SPRA 方法中,需依據核電廠所在廠址之危害度分析決定出8 個由小至大之地震強度等級,據以進行非線性動力分析。然而8 個強度等級是否足夠或過多,卻未曾進行評估。此外,對於土壤結構互制效應、增廣所造成之不確定性及增廣列數亦未曾討論。
本研究將以Huang 與Whittaker 等人發表之SPRA 新方法,對範例電廠進行地震機率式風險評估,藉此探討此方法程序中之優缺點與改進的可能性。並對案例電廠中之餘熱移除系統進行反力牆反覆載重試驗,了解該系統之耐震行為,試驗及分析結果可用於未來研究,建立該系統以結構反應為參數之易損性曲線。本研究結果顯示:1) 使用蒙地卡羅模擬可大幅降低計算時間;2) 考量結構不確定性所計算之風險值較低;3) 增廣矩陣中識別發生目標事件之平均列數與對數標準差為對數線性關係,可據此決定增廣需求矩陣之列數與計算次數;4) SAP2000 分析軟體對於管線之模擬可靠性高,可用於後續建立易損性曲線。 | zh_TW |
dc.description.abstract | Seismic probabilistic risk assessment (SPRA) has been widely used to compute the frequencies of core damage and release of radiation of a nuclear power plant (NPP). In 2011, Huang, Whittaker, and Luco published a SPRA methodology with the following characteristics different from the widely used Zion method: (a) seismic fragility curves are defined as a function of structural response parameters; (b) nonlinear response-history analysis is used to estimate seismic demands for components of NPPs; (c) generating a large number of simulations through statistical manipulation of a relatively small number of structural analyses; (d) Monte Carlo simulation is used to determine damage states of components.
In the study presented in this paper, the seismic risk of a sample NPP was evaluated using the methodology published by Huang, Whittaker, and Luco, and the pros and cons of the methodology will be discussed. The seismic risk studied herein was defined as the annual frequency of unacceptable performance of a sample accident sequence for the sample NPP. Variations in the strength of structural and non-structural components,damping and soil properties are directly considered in the numerical models used in response-history analysis. The procedure to determine the minimum number of structural analyses was also presented in this study. In this study, the seismic performance of a critical piping system in the sample NPP was evaluated numerically and experimentally. The results will be used to establish the response-based fragility curve for the piping system in the next stage of this study. | en |
dc.description.provenance | Made available in DSpace on 2021-05-15T17:52:16Z (GMT). No. of bitstreams: 1 ntu-103-R01521221-1.pdf: 7944114 bytes, checksum: 75e6bade14a344f084d61cfc50e90ac2 (MD5) Previous issue date: 2014 | en |
dc.description.tableofcontents | 口試委員審定書 i
誌謝 ii 摘要 iii ABSTRACT iv 目錄 v 表目錄 x 圖目錄 xii 第一章 緒論 1 1.1 研究背景與動機 1 1.2 研究目的 2 1.3 文獻回顧 3 1.3.1 核電廠耐震安全評估方法 3 1.3.2 地震機率式風險評估 3 1.3.3 管線系統試驗與模擬 5 1.4 論文結構 6 第二章 新一代地震機率式風險評估 9 2.1 核電廠系統分析 10 2.2 地震危害度分析 11 2.3 非線性反應歷時分析 12 2.4 元件損傷評估 13 2.5 地震風險量化計算 14 第三章 案例核電廠介紹與數值模型 20 3.1 反應爐廠房 20 3.1.1 結構系統 20 3.1.2 數值分析模型 21 3.1.2.1 結構載重設定 21 3.1.2.2 轉動慣量設定(Rotational Inertia) 21 3.1.2.3 柱斷面性質設定 22 3.1.2.4 樓板勁度及質量設定 22 3.1.2.5 非線性塑鉸設定 23 3.1.2.6 土壤-結構互制效應分析 23 3.2 控制廠房 25 3.2.1 結構系統 26 3.2.2 數值分析模型 26 3.2.2.1 結構重量設定 26 3.2.2.2 轉動慣量設定 26 3.2.2.3 柱斷面性質設定 26 3.2.2.4 樓板勁度及質量設定 27 3.2.2.5 非線性塑鉸設定 27 3.2.2.6 土壤-結構互制效應 27 第四章 地震機率式風險評估示範例 41 4.1 系統分析 41 4.2 地震危害度及地震歷時之選取與縮放 42 4.3 反應歷時分析 43 4.3.1 最佳預測之反應歷時分析 43 4.3.2 考量結構不確定性之反應歷時分析 44 4.3.2.1 考量結構阻尼比之不確定性 44 4.3.2.2 考量塑絞之不確定性 44 4.3.2.3 考量土壤與結構之互制效之不確定性 45 4.4 元件損傷評估並計算目標事件發生機率 45 4.4.1 方法一:以各元件之破壞機率直接計算目標發生機率 45 4.4.2 方法二:以增廣需求矩陣進行蒙地卡羅試驗 46 4.4.3 方法三:以增廣需求矩陣之元件破壞機率用布林代數計算 48 4.5 風險計算 50 4.6 目標事件發生機率及風險計算結果討論 50 4.6.1 目標事件發生機率於三種方式計算結果之差異 50 4.6.2 於模型中考量結構不確定性之影響 51 4.6.3 增廣矩陣列數之討論 53 4.6.3.1 方法二增廣矩陣列數討論 53 4.6.3.2 方法三增廣矩陣列數討論 55 4.6.3.3 方法二及方法三之增廣列數比較 56 4.6.4 危害度曲線依地震強度分段討論 57 4.6.4.1 結構最佳預測之分段討論 57 4.6.4.2 考量結構不確定性之分段討論 58 第五章 餘熱移除系統介紹與試驗配置 97 5.1 餘熱移除系統介紹 97 5.2 試驗管線段介紹 98 5.3 試驗配置介紹 100 5.4 試驗設計介紹 100 5.4.1 施力設備 101 5.4.2 水壓控制設備 101 5.4.3 試體規格說明 102 5.5 試驗儀器擺置說明 103 5.5.1 角度計 103 5.5.2 應變計 104 5.5.3 荷重計 104 5.5.4 水壓計 105 5.5.5 影像量測系統(NDI) 105 5.6 試驗測試波介紹 105 第六章 實驗結果分析與數值模擬比較 126 6.1 試驗結果與分析 126 6.1.1 荷重計 126 6.1.2 角度計 128 6.1.3 應變計 128 6.1.4 影像量測系統(NDI) 129 6.1.5 水壓計 130 6.2 數值模型建立 130 6.2.1 模型材料與尺寸參數設定 130 6.2.2 邊界條件之模型參數設定 131 6.2.2.1 考量荷重計之變形 131 6.2.2.2 考量彈簧支撐架受力之方向 132 6.3 數值模型與試驗結果比對 133 第七章 結論與建議 163 7.1 結論 163 7.2 建議 165 7.2.1 考量結構不確定性 165 7.2.2 需求矩陣增廣列數 165 7.2.3 危害度曲線分段數 165 7.2.4 餘熱移除系統之安全性 166 7.3 未來工作 166 參考文獻 167 附錄A 應變計試驗結果 172 附錄B 影像量測系統(NDI)試驗結果 185 | |
dc.language.iso | zh-TW | |
dc.title | 新一代核能電廠耐震機率式風險評估與餘熱移除系統耐震行為研究 | zh_TW |
dc.title | Seismic Probabilistic Risk Assessment of Nuclear Power
Plants Using Response-Based Fragility Functions and Seismic Behavior of Residual Heat Removal System | en |
dc.type | Thesis | |
dc.date.schoolyear | 102-2 | |
dc.description.degree | 碩士 | |
dc.contributor.oralexamcommittee | 柴駿甫(Juin-Fu Chai),卿建業(Jian-ye Ching) | |
dc.subject.keyword | 地震機率式風險評估,蒙地卡羅模擬法,餘熱移除系統, | zh_TW |
dc.subject.keyword | seismic probabilistic risk assessment,Monte Carlo Simulation,residual heat removal piping system, | en |
dc.relation.page | 197 | |
dc.rights.note | 同意授權(全球公開) | |
dc.date.accepted | 2014-08-12 | |
dc.contributor.author-college | 工學院 | zh_TW |
dc.contributor.author-dept | 土木工程學研究所 | zh_TW |
顯示於系所單位: | 土木工程學系 |
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