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  • 學位論文

核電廠電氣盤體之振動台試驗與模擬分析

The shaking table test and numerical simulation of MCC cabinet in Nuclear Power Plant

指導教授 : 廖文義

摘要


臺灣核能電廠運轉至今已有一段時間,期間核能電廠電氣盤體之盤內設備物需多次更新汰換及維護。本研究以臺灣某核能電廠餘熱移除系統C串(RHR-C,Residual Heat Removal)之馬達控制中心(MCC,Motor control center)電氣盤體機櫃作為研究對象,藉由振動台試驗了解MCC電氣盤體於受震下之動力反應與結構特性,試驗目的主要為探討以下項目:(一)、空櫃與櫃內含設備物之動力反應特性;(二)、不同量測位置(如:機櫃內外部及不同高程處之反應比較);(三)輸入波強度之影響;(四)櫃內有無抽屜型式之機櫃動力反應;(五)不同形式輸入地震波(如:主要涵蓋頻率範圍不同)對機櫃行為之影響。 除了探討臺灣核能電廠MCC電氣盤體之結構動力特性與盤內反應,另依據試驗機櫃之材料性質及尺寸進行電氣盤體動力反應之數值模擬,研究採用SAP2000分析軟體進行模型建立及動態反應模擬,其目的為模擬真實機櫃受震時之反應,並可提供往後參數分析及多盤體機櫃模擬之參考。

並列摘要


In this study, a seismic behavior of the electrical cabinet in Nuclear Power Plants (NPPs) was evaluated by the shaking table test. A Residual Heat Removal System of C loop (RHR-C) for the Motor Control Center (MCC) cabinet was selected by Taiwan Nuclear Power Plant of FSAR report, and a real MCC cabinet for the Taiwan Nuclear Power Plant site was built same full size. In addition, five variable conditions and the associated effects on the structural characteristics of MCCs were specified and discussed: (1) original bare cabinets or the ones with additional mass blocks simulating in-cabinet equipment, (2) different measurement locations, (3) different input shaking levels, (4) cabinets with or without drawers, and (5) different types of required response spectrum (RRS). In order to understand the dynamic characteristics and In-cabinet response spectrum of the MCCs. According to the tensile testing can obtain the material property and dimension of cabinets to doing the numerical simulation. Using the SAP2000 analysis software to estimate the numerical model and simulate the dynamic response. The purpose of the numerical model and estimate that simulate real cabinet on the earthquake, and providing future parametric analysis and multi-cabinet simulation.

參考文獻


[1]Min Kyu Kim , In-Kil Choi , Jeong-Moon Seo ,Nuclear Engineering and Design, Nuclear Engineering and Design 341-355,2012.
[2]NURGE/CR-5203, Dynamic Amplification of Electrical Cabinets. U.S. National Technical Information Service, June 1988.
[7]T. Y. Chang, Seismic qualification of equipment in operating nuclear power plants, USNRE, NUREG-1030, 1985.
[8]Shi Z.T., A simplified approach to generate in-cabinet amplified response spectrum , Raytheon Engineers and Constructors, Transactions of the 14th International Conference on Structural Mechanics in Reactor Technology (SMiRT 14), Lyon, France, August 17-22, 1997.
[9]Abhinav Gupta, S.K. Rustogi, Ajaya K. Gupta, Ritz vector approach for evaluating incabinet response spectra, Center for Nuclear Power Plant Structures, Equipment and Piping, North Carolina State University, Nuclear Engineering and Design vol. 190, p.p. 255–272, 1999.

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