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Influence of Differences Between Seismic Safety Evaluation Methods for Equipment and Piping of a Nuclear Facility

[+] Author Affiliations
Akemi Nishida

Japan Atomic Energy Agency, Kashiwa, Japan

Kazuhiko Iigaki, Kazuhiro Sawa

Japan Atomic Energy Agency, Oarai, Japan

Yinsheng Li

Japan Atomic Energy Agency, Tokai, Japan

Paper No. PVP2015-45913, pp. V008T08A014; 7 pages
doi:10.1115/PVP2015-45913
From:
  • ASME 2015 Pressure Vessels and Piping Conference
  • Volume 8: Seismic Engineering
  • Boston, Massachusetts, USA, July 19–23, 2015
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-5703-8
  • Copyright © 2015 by ASME

abstract

The objective of this research was to investigate the influence of differences between methods for evaluating the seismic safety of the equipment and piping of a nuclear facility. For the input ground motion, one wave was chosen from among 200 waves of input ground motions of maximum acceleration of 700–1100 cm/s2 created for the Oarai District of the Ibaraki Prefecture. Seismic safety evaluations were performed using the conventional method, which relies on floor response spectrum data, and using the multi-input method. The differences between the two methods were summarized. The target equipment and piping system were cooling systems in a model plant. It was found that the response predicted by the multi-input method was approximately half of the response predicted by the conventional method. The third trial evaluation method using the floor response of a three-dimensional building model as input was also reported.

Copyright © 2015 by ASME

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