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Development of Structural Integrity Assessment Method for Flow-Induced Vibration of Reactor Internals in PWR

[+] Author Affiliations
Hirokazu Sugiura

Mitsubishi Heavy Industries, Ltd., Kobe, Japan

Shigeyuki Watanabe

Mitsubishi Heavy Industries, Ltd., Tokyo, Japan

Akihisa Iwasaki, Hideyuki Morita, Hideyuki Sakata

Mitsubishi Heavy Industries, Ltd., Takasago, Japan

Yoshito Nishikawa

Kansai Electric Power Co., Inc., Osaka, Japan

Paper No. PVP2018-84473, pp. V004T04A006; 8 pages
  • ASME 2018 Pressure Vessels and Piping Conference
  • Volume 4: Fluid-Structure Interaction
  • Prague, Czech Republic, July 15–20, 2018
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-5165-4
  • Copyright © 2018 by ASME


For verifying the structural integrity of the reactor internals (RIs) in a pressurized water reactor (PWR) plant, it is important to estimate the vibration response of the core barrel (CB) due to flow turbulence. Instead of scale model test, the computational fluid dynamics (CFD) has been expected as a method to predict the turbulence forcing function for the response analysis of the CB. In this article, a hybrid approach combining empirical equations based on flow test and CFD analysis is proposed in order to predict the turbulence forcing function.

The scale model test of new RIs, which were developed by Mitsubishi Heavy Industries, Ltd., was conducted, and the pressure fluctuations for the turbulence forcing function and the vibration response of the CB were measured. The pressure fluctuations were calculated by CFD analysis, and the vibration analysis using the turbulence forcing function determined from the calculated pressure fluctuations was performed.

This article provides the scale model test data and the empirical equations of the turbulence forcing functions, and validation results of the proposed method to predict the turbulence forcing function using CFD.

Copyright © 2018 by ASME



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