Seismic Qualification By Analysis Of A Nuclear Class Horizontal ...

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Open Access
Issue E3S Web Conf. Volume 180, 2020 9th International Conference on Thermal Equipments, Renewable Energy and Rural Development (TE-RE-RD 2020)
Article Number 01001
Number of page(s) 12
Section Thermal Equipments and Processes
DOI https://doi.org/10.1051/e3sconf/202018001001
Published online 24 July 2020
  1. ANSYS 19 documentation [Google Scholar]
  2. Seismic Design Classification, Regulatory Guide 1.29, U.S. Nuclear Regulatory Commission, (2007). [Google Scholar]
  3. US NRC Regulatory Guide 1.92, Combining Modal Responses and Spatial Components in Seismic Response Analysis, Rev.2, (2006). [Google Scholar]
  4. Safety Standards Series No.NS-G-1.6, Seismic Design and Qualification for Nuclear Power Plants Safety Guide [Google Scholar]
  5. EPRI, Recommended Piping Seismic Adequacy Criteria Based on Performance During and after Earthquakes, Report NP-5617, January 1988 [Google Scholar]
  6. US NUCLEAR REGULATORY COMMISSION, Seismic fragility test of a 6-inch diameter pipe system, NUREG/CR-4859 (1988) [Google Scholar]
  7. SEISMIC QUALIFICATION UTILITY GROUP (SQUG), Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment, February 1992 [Google Scholar]
  8. EPRI, NP-7500-SL, The October 17, 1989 Loma Prieta Earthquake: Effects on selected power and industrial facilities, September 1991 [Google Scholar]
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