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Seismic Test Results of the Main Steam Safety Relief Valve for Japanese Boiling Water Reactor Nuclear Power Plants

[+] Author Affiliations
Koji Nishino, Kazuyoshi Yonekura, Nobuo Kojima, Yukio Watanabe

Toshiba Corporation, Yokohama, Japan

Yoshitaka Tsutsumi

Chubu Electric Power Co., Nagoya, Japan

Shin Kumagai

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

Paper No. PVP2017-65602, pp. V008T08A021; 5 pages
doi:10.1115/PVP2017-65602
From:
  • ASME 2017 Pressure Vessels and Piping Conference
  • Volume 8: Seismic Engineering
  • Waikoloa, Hawaii, USA, July 16–20, 2017
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-5803-5
  • Copyright © 2017 by ASME

abstract

The functional requirements of Main Steam Safety Relief Valves (SRVs) provided in Boiling Water Reactor (BWR) nuclear power plants in Japan have been previously evaluated via seismic tests and so forth; however, since the response acceleration has increased in line with a recent reassessment of standard earthquake ground motions, it is necessary to evaluate seismic operability with respect to high acceleration. In addition, from the viewpoint of equipment fragility in seismic PRA also, it is necessary to determine the practical seismic operability limits.

We used a resonant shaking table in the Central Research Institute of the Electric Power Industry (CRIEPI) [1], which is capable of seismic tests at acceleration levels that have been unachievable until now, and in seismic tests carried out on an SRV, we obtained results confirming that validated seismic operability was possible even at response accelerations as high as 20×9.8 m/s2.

The seismic operability results obtained for this SRV will be applied to a fragility analysis of seismic PRA.

Copyright © 2017 by ASME

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