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

has been cited by the following article:

• TITLE: Study on Seismic Fragility Analysis for Piping of CEFR

  AUTHORS: Zhiwei Fu, Yahua Qiao, Long Tang, Yan Chen, Jiaxu Zuo

  KEYWORDS: Seismic Fragility; Fragility Parameter; CEFR Accident Residual Heat Removal System; 3D Model

  JOURNAL NAME: Journal of Applied Mathematics and Physics, Vol.1 No.6, December 3, 2013

  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.