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Development of a Thermal Fatigue Screening and Evaluation Methodology for Pressurized Water Reactor Plants

[+] Author Affiliations
J. D. Keller, A. J. Bilanin

Continuum Dynamics, Inc., Ewing, NJ

S. T. Rosinski

Electric Power Research Institute, Charlotte, NC

Paper No. PVP2004-2995, pp. 217-228; 12 pages
doi:10.1115/PVP2004-2995
From:
  • ASME/JSME 2004 Pressure Vessels and Piping Conference
  • Elevated Temperature Design and Analysis, Nonlinear Analysis, and Plastic Components
  • San Diego, California, USA, July 25–29, 2004
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4667-9
  • Copyright © 2004 by ASME

abstract

Thermal cycling has been identified as a mechanism that can potentially lead to fatigue cracking in un-isolable branch lines attached to pressurized water reactor (PWR) primary coolant piping. A significant research and development program has been undertaken to understand the mechanisms causing thermal cycling and to develop models for predicting the thermal-hydraulic boundary conditions for use in piping structural and fatigue analysis. A combination of first-principles engineering modeling and scaled experimental investigations has been used to formulate improved thermal cycling modeling tools. This paper will provide an overview of the model development program, a summary of the supporting test program, and a description of the thermal cycling model structure. Benchmarking of the thermal cycling model against several PWR plant configurations is presented, demonstrating favorable comparison with cases where thermal stratification and cycling has been previously observed.

Copyright © 2004 by ASME

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