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Development of Advanced Fatigue Evaluation Methodology for Monitoring Major Components in Nuclear Power Plant

[+] Author Affiliations
W. Kim, Jongjooh Kwon, Tae-Ryong Kim

Korea Electric Power Research Institute, Daejeon, Korea

Hong Tae Kang

University of Michigan, Dearborn, MI

Gyeong-Hoi Koo

Korea Atomic Energy Research Institute, Daejeon, Korea

Paper No. PVP2010-25585, pp. 19-26; 8 pages
doi:10.1115/PVP2010-25585
From:
  • ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference
  • ASME 2010 Pressure Vessels and Piping Conference: Volume 7
  • Bellevue, Washington, USA, July 18–22, 2010
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-4926-2 | eISBN: 978-0-7918-3878-5
  • Copyright © 2010 by ASME

abstract

In an attempt to develop fatigue monitoring system, two improved fatigue evaluation schemes have been proposed to monitor fatigue degradation in major components and piping of the pressurized water reactor. Proposed methods are both aimed to obtain realistic fatigue usage factors for given plant transients. Developed schemes utilize plant operating signals such as coolant temperature, pressure and flow rate. Finite element method and an improved Green’s function approach were used to calculate stresses and fatigue usage. Case studies were performed to validate effectiveness of each proposed scheme. It has been confirmed that proposed schemes can effectively reduce excessive conservatism in estimating fatigue usage and improve accuracy in stress calculation.

Copyright © 2010 by ASME

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