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  • 學位論文

核能電廠結構元件易損性分析方法研究-以輔助廠房為例

Fragility Analysis for Structures in Nuclear Power Plants-An Example of an Auxiliary Building

指導教授 : 黃尹男

摘要


Huang, Whittaker與Luco等人於2011年發表了一套新的地震機率式風險評估(Seismic Probabilistic Risk Assessment, SPRA)方法,此法結合了核電廠既有的SPRA方法與地震工程學界近年的發展,其中包含五個步驟:(1)系統分析及元件易損性分析、(2)危害度分析、(3)結構動力歷時反應分析、(4)元件損傷評估與(5)地震風險量化計算。在元件易損性分析的部分,HWL-typed SPRA配合結構非線性動力歷時反應分析,藉由分析將原本傳統SPRA使用分離變數法所考量之結構反應參數之變異性納入考量,可以表現出各因子之間的關係,而分離變數法將所有影響結構反應之因素視為獨立行為,並未考量各因子之間的相關性。 本研究針對結構易損性分析方法進行探討,依案例電廠之結構為例,依照傳統分離變數法所考量之各因子中位數與不確定性,建立可靠之數值模型,再藉由多個數值模型之非線性動力歷時分析資料,以三種數值分析方式:線性迴歸法、最大可能性估計法與增量動力分析法,建立以地表最大加速度與結構基頻之譜加速度的易損性曲線,討論(1)四種取得易損性曲線的方法之間的差異與(2)各因子之不確定性考量與否對易損性曲線的影響。本研究結果顯示與傳統分離變數法之結果相比,以動力分析結果計算得之易損性曲線結果差異不大,但可降低對數標準差,顯示在考量了因子之間的相關性後,可降低對於結構反應的不確定性,而三種不同分析方式的結果則差異不大。另外,由於核電廠結構強韌,易損性曲線的中位數大,故對於目前與案例電廠地質條件相近且可能影響核電廠安全性的地震,使用傳統分離變數法建立之地震易損性曲線所取得的破壞機率較大,而進行非線性動力分析並以其結果取得的破壞機率較小。

並列摘要


Seismic probabilistic risk assessment(SPRA) has been widely used to compute the frequency of core damage and release of radiation of a nuclear power plant(NPP). In 2011, Huang, Whittaker and Luco published a new SPRA methodology, different from existing SPRA, including using nonlinear response-history analysis of structure to consider the relationships between each factor, which is considered independent during separation of variable method. In the study, the numerical model based on uncertainty and randomness from separation of variable method is used to develop a fragility curve for the system with three different fragility analysis method: regression analysis, maximum likelihood estimation and incremental dynamic analysis. Comparing to separation of variable method, the result of numerical simulation method is similar but much more reliable. The three different numerical analysis method get similar result. Thus recommendation is using numerical simulation fragility curve to consider relationships between each factor in seismic probabilistic risk assessment, which can get precise fragility curve.

參考文獻


American Society of Civil Engineers (ASCE). (2014). “Seismic analysis of safe-ty-related nuclear structures.” ASCE 41-13, American Society of Civil Engineers , Reston, Virginia.
American Society of Civil Engineers (ASCE). (2017). “Seismic analysis of safe-ty-related nuclear structures.” ASCE 4-16, American Society of Civil Engineers , Reston, Virginia.
Baker,J.W. (2013). “Probabilistic seismic hazard analysis” white paper version
Campbell, R., Hardy, G., and Merz, K. (2002). “Seismic fragility application guide.” TR-1002988, Electric Power Research Institute, Palo Alto, CA.
Chao S.-H., Chiou B., Hsu C.-C., Lin P.-S. (2019). “Development of horizontal and vertical ground motion models for crustal earthquakes and subduction earthquakes in Taiwan” NCREE-19-003

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