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3 edition of Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels found in the catalog.

Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels

Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels

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Published by Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Supt. of Docs., U.S. G.P.O. [distributor] in Washington, DC .
Written in English

    Subjects:
  • Austenitic stainless steel -- Fatigue.,
  • Light water reactors -- Materials.

  • Edition Notes

    Statementprepared by O.K. Chopra.
    ContributionsU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Argonne National Laboratory.
    The Physical Object
    FormatMicroform
    Paginationxi, 42 p.
    Number of Pages42
    ID Numbers
    Open LibraryOL15546526M

    Formulas for calculating the environmental fatigue penalty factors were provided in NUREG/CR “Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels” March , for carbon and low-alloy steels and in NUREG/CR “Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Recent test data illustrate potentially significant effects of LWR environments on the fatigue resistance of carbon and low-alloy steels and austenitic stainless steels (SSs). Under certain loading and://metadc/m2/1/high_res_d/pdf.

    in nuclear-grade carbon steels, low alloy steels and austenitic stainless steels. [12] Chopra O K, Shack W J. Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels [A]. Nuclear Regulatory Commission[C However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life (ε-N) data illustrate potentially

    Chopra O K. Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels [R]. NUREG/CR, ANL/31, Washington D. C.: Nuclear Regulatory Commission, [11] However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Recent test data illustrate potentially significant effects of LWR environments on the fatigue resistance of carbon and low-alloy steels and austenitic stainless steels (SSs).


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Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels Download PDF EPUB FB2

EFFECTS OF LWR COOLANT ENVIRONMENTS ON FATIGUE DESIGN CURVES OF AUSTENITIC STAINLESS STEELS by O. Chopra Abstract The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components.

Figures I– through I– of Appendix I to Section III of the Code specify fatigue design curves for structural   EFFECTS OF LWR COOLANT ENVIRONMENTS ON FATIGUE DESIGN CURVES OF AUSTENITIC STAINLESS STEELS by 0.

Chopra Abstract The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures through of Appendix I to Section III of the Code   EFFECTS OF LWR COOLANT ENVIRONMENTS ON FATIGUE DESIGN CURVES OF AUSTENITIC STAINLESS STEELS by 0.

Chopra Abstract The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures I through of Appendix I to Section III of the Code   EFFECTS OF LWR COOLANT ENVIRONMENTS ON FATIGUE DESIGN CURVES OF AUSTENITIC STAINLESS STEELS by 0.

Chopra Abstract The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures through of Appendix I to Section III of the Code specify fatigue design curves for structural 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 austenitic stainless steels in light water reactor (LWR) :// Technical Report: Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels This paper reviews the existing fatigue ε–N data for carbon and low–alloy steels and austenitic stainless steels in LWR coolant environments.

The effects of key material, loading, and environmental parameters, such as steel type, strain amplitude, strain rate, temperature, dissolved oxygen level in water, flow rate, surface finish, and The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code specifies design curves for the fatigue life of structural materials in nuclear power plants.

H   fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves.

Existing fatigue strain–vs.–life (ε–N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and Get this from a library. Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels.

[O K Chopra; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.; Argonne National Laboratory.] EFFECTS OF LWR COOLANT ENVIRONMENTS ON FATIGUE LIVES OF AUSTENITIC STAINLESS STEELS Omesh K.

Chopra and Daniel J. Gavenda Energy Technology Division Argonne National Laboratory Argonne, Illinois ABSTRACT The ASME Boiler and Pressure Vessel Code fatigue design curves for structural materials do not explicitly address the effects of reactor ://metadc/m2/1/high_res_d/pdf.

austenitic SSs in air and LWR environments are discussed. Experimental Fatigue tests have been conducted on Types NG and SS to establish the effects of LWR coolant environments on fatigue lives of these steels.

The composition of the two steels is given in Table 1. Smooth cylindrical specimens with mm diameter and 19–mm gauge://metadc/m2/1/high_res_d/pdf. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves.

Existing fatigue strain–vs.–life (ε–N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping :// Technical Report: Effects of LWR coolant environments on fatigue lives of austenitic stainless   Chopra O K.

Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels [R]. NUREG/CR, ANL/31, Washington   The ASME Boiler and Pressure Vessel Code fatigue design curves for structural materials do not explicitly address the effects of reactor coolant environments on fatigue life.

Recent test data indicate a significant decrease in fatigue life of pressure vessel and piping materials in light water Fatigue tests have been conducted on Types and NG stainless steels to evaluate the effects of various material and loading variables, e.g., steel type, strain rate, dissolved oxygen (DO) in water, and strain range, on the fatigue lives of these ://   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) ://   Existing fatigue strain-vs.-life ({var_epsilon}-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels.

This report provides an overview of fatigue crack initiation in austenitic stainless steels in LWR coolant :// Recent test data illustrate potentially significant effects of light water reactor (LWR) coolant environments on the fatigue resistance of carbon and low-alloy steels.

The crack initiation and crack growth characteristics of carbon and low-alloy steels in LWR environments are ://. effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves.

Existing fatigue strain–vs.–life (e–N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of carbon and low–alloy steels,1–14 as well as austenitic stainless steels (SSs However, the effects of light water reactor coolant environments are Start Printed Page not explicitly addressed by the Code design curves.

The existing fatigue strain-vs.-life data illustrate potentially significant effects of light water reactor coolant environments on the fatigue resistance of pressure vessel and piping ://The existing fatigue strain–vs.–life (ε–N) data illustrate potentially significant effects of light water reactor (LWR) coolant environments on the fatigue resistance of pressure vessel and