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

Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels [electronic resource]

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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 explicitl...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Oak Ridge, Tenn. : distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1998.
Subjects:
Carbon Steels.
Low Alloy Steels.
Fatigue.
Bwr Type Reactors.
Pwr Type Reactors.
Reactor Materials.
Coolants.
Crack Propagation.
Water Chemistry.
Corrosive Effects.
Corrosion Fatigue.
Experimental Data.
Materials Science ;21 Nuclear Power Reactors And Associated Plants.

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Call Number: E 1.99:ANL--97/18
E 1.99:ANL--97/18 Available

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