JAMP  Vol.1 No.6 , November 2013
Study on Seismic Fragility Analysis for Piping of CEFR
Abstract: This paper introduces the conception of seismic fragility, gives the model of seismic fragility analysis, and places emphasis on discussing quantization process of seismic fragility parameters. Then, establishes 3D model of pipes of Chinese Experimental Fast Reactor (CEFR) accident residual heat removal system, and obtains the stresses which are essential for calculating seismic fragility parameters. Finally, combined with quantitative methods of seismic fragility, calculates the safety factors and uncertainties of CEFR pipeline, and obtains the system seismic fragility parameters: Am = 2.42 g, βr = 0.36, βu = 0.44, HCLPF = 0.65 g. The results show that: the pipeline of CEFR accident residual heat removal system has high seismic capacity.
Cite this paper: Fu, Z. , Qiao, Y. , Tang, L. , Chen, Y. and Zuo, J. (2013) Study on Seismic Fragility Analysis for Piping of CEFR. Journal of Applied Mathematics and Physics, 1, 82-88. doi: 10.4236/jamp.2013.16016.

[1]   [1] Z. W. Fu, “Study on Seismic Fragility Analysis for CEFR Accident Residual Heat Removal System,” China Institute of Atomic Energy, Beijing, 2013.

[2]   CIAE, “Final Safety Analysis Report for China Experimental Fast Reactor,” China Institute of Atomic Energy, Beijing, 2008.

[3]   EPRI, EPRI-1002989, “Seismic Probabilistic Risk Assessment Implementation Guide,” 2009.

[4]   EPRI, EPRI 1019200, “Seismic Fragility Application Update Guide,” Palo Alto, 2009.

[5]   EPRI, EPRI-TR-103959, “Methodology for Developing Seismic Fragilities,” Palo Alto, 1994.

[6]   EPRI, EPRI-1002988, “Seismic Fragility Application Guide,” Electric Power Research Institute (EPRI), Palo Alto, 2002.

[7]   Z. W. Fu, D. H. Zhang, C. M. Zhang, et al., “Study on Equipment Seismic Fragility Analysis Method,” Nuclear Science and Engineering, Vol. 33, No. 2, 2013, pp. 213- 218.

[8]   N. M. Newmark and W. J. Hall, “Development of Criteria for Seismic Review of Selected Nuclear Power Plants,” NUREG/CR-0098, 1978.

[9]   USNRC, “Regulatory Guide 1.60 Design Response Spectra for Seismic Design of Nuclear Power Plants,” 1973

[10]   ASME, “ASME II-D Performance,” 2004.

[11]   DOE, “Natural Phenomena Hazard Design and Evaluation Criteria for Department of Energy Facilities,” DOE- STD-1020-2002: DOE STANDARD, 2002.