Application of environmentally-corrected fatigue curves to nuclear power plant components

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Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four US nuclear steam ... continued below

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10 p.

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Ware, A.G.; Morton, D.K. & Nitzel, M.E. June 1, 1996.

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Description

Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four US nuclear steam supply system vendors. For each facility, six locations were studied including two locations on the reactor pressure vessel. In addition, there are older vintage plants where components of the reactor coolant pressure boundary were designed to codes that did not require an explicit fatigue analysis of the components. In order to assess the fatigue resistance of the older vintage plants, an evaluation was also conducted on selected components of three of these plants. This paper discusses the insights gained from the application of the interim fatigue curves to components of seven operating nuclear power plants.

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10 p.

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INIS; OSTI as DE96009012

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  • American Society of Mechanical Engineers (ASME) pressure vessels and piping conference, Montreal (Canada), 21-26 Jul 1996

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  • Other: DE96009012
  • Report No.: INEL--96/00105
  • Report No.: CONF-960706--10
  • Grant Number: AC07-94ID13223
  • Office of Scientific & Technical Information Report Number: 244601
  • Archival Resource Key: ark:/67531/metadc669594

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • June 1, 1996

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  • June 29, 2015, 9:42 p.m.

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  • April 7, 2016, 7:35 p.m.

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Ware, A.G.; Morton, D.K. & Nitzel, M.E. Application of environmentally-corrected fatigue curves to nuclear power plant components, article, June 1, 1996; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc669594/: accessed September 25, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.