Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels

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Description

The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures I-9.1 through I-9.6 of Appendix I to Section III of the code specify fatigue design curves for structural materials. While effects of reactor coolant environments are not explicitly addressed by the design curves, test data indicate that the Code fatigue curves may not always be adequate in coolant environments. This report summarizes work performed by Argonne National Laboratory on fatigue of carbon and low-alloy steels in light water reactor (LWR) environments. The existing fatigue S-N data have been evaluated to establish the ... continued below

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125 p.

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Chopra, O. K. & Shack, W. J. March 1998.

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Description

The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures I-9.1 through I-9.6 of Appendix I to Section III of the code specify fatigue design curves for structural materials. While effects of reactor coolant environments are not explicitly addressed by the design curves, test data indicate that the Code fatigue curves may not always be adequate in coolant environments. This report summarizes work performed by Argonne National Laboratory on fatigue of carbon and low-alloy steels in light water reactor (LWR) environments. The existing fatigue S-N data have been evaluated to establish the effects of various material and loading variables such as steel type, dissolved oxygen level, strain range, strain rate, temperature, orientation, and sulfur content on the fatigue life of these steels. Statistical models have been developed for estimating the fatigue S-N curves as a function of material, loading, and environmental variables. The results have been used to estimate the probability of fatigue cracking of reactor components. The different methods for incorporating the effects of LWR coolant environments on the ASME Code fatigue design curves are presented.

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125 p.

Notes

INIS; OSTI as TI98002917

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  • Other Information: PBD: Mar 1998

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  • Other: TI98002917
  • Report No.: NUREG/CR--6583
  • Report No.: ANL--97/18
  • Grant Number: W-31109-ENG-38
  • DOI: 10.2172/573404 | External Link
  • Office of Scientific & Technical Information Report Number: 573404
  • Archival Resource Key: ark:/67531/metadc695900

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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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  • March 1998

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  • Aug. 14, 2015, 8:43 a.m.

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  • April 8, 2016, 8:04 p.m.

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Chopra, O. K. & Shack, W. J. Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels, report, March 1998; Washington D.C.. (digital.library.unt.edu/ark:/67531/metadc695900/: accessed November 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.