Review of environmental effects on fatigue crack growth of austenitic stainless steels.
Description:
Fatigue and environmentally assisted cracking of piping, pressure vessel cladding, and core components in light water reactors are potential concerns to the nuclear industry and regulatory agencies. The degradation processes include intergranular stress corrosion cracking of austenitic stainless steel (SS) piping in boiling water reactors (BWRs), and propagation of fatigue or stress corrosion cracks (which initiate in sensitized SS cladding) into low-alloy ferritic steels in BWR pressure vessel…
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Date:
July 11, 1994
Creator:
Shack, W. J.; Kassner, T. F. & Technology, Energy
Item Type:
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Report
Partner:
UNT Libraries Government Documents Department