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Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities: Part 5 — Fatigue Test of the Crossover Piping

[+] Author Affiliations
Kotoyo Mizuno, Hiroshi Shimizu

Mitsubishi Heavy Industries, Ltd., Takasago, Hyogo, Japan

Masakazu Jimbo

Toshiba Corporation, Yokohama, Kanagawa, Japan

Naohiko Oritani

Hitachi-GE Nuclear Energy Co., Ltd., Hitachi, Ibaraki, Japan

Shigenobu Onishi

Chubu Electric Power Co., Inc., Nagoya, Aichi, Japan

Paper No. PVP2014-29032, pp. V008T08A039; 9 pages
doi:10.1115/PVP2014-29032
From:
  • ASME 2014 Pressure Vessels and Piping Conference
  • Volume 8: Seismic Engineering
  • Anaheim, California, USA, July 20–24, 2014
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-4607-0
  • Copyright © 2014 by ASME

abstract

This paper provides a part of the series of “Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities”.

It is assumed the main steam crossover piping is damaged by the ratcheting deformation based on the relative displacement and the inertia load by the earthquake between the buildings and the internal pressure.

This part shows a low cycle ratcheting fatigue test using the scaling model under the combined loadings based on the relative displacement and the inertia load by the earthquake between the buildings and analyses were performed to confirm the failure modes and the fatigue life of the pipe elbow for the fatigue damage of the long-period ground motion.

As a result, the fatigue life under combined loads was sufficiently higher than the design criteria and analyses are good match with the test results. So, it confirmed the structural integrity of the crossover piping.

Copyright © 2014 by ASME

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