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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… more
Date: July 11, 1994
Creator: Shack, W. J.; Kassner, T. F. & Technology, Energy
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Reactor Core Materials for a Gas-Cooled Reactor Experiment

Description: An evaluation of core materials for a gas-cooled reactor is being made. Work on the ZrH/sub n/ moderator has been confined to the high-hydrogen or delta- phase material. Methods for preparing sound hydride bodies of the highhydrogen composition have been developed. Both solid hydride and hydride powder compacts are being clad by a pressure-bonding technique. The hot hardness, tensile strength, thermal conductivity, thermal-expansion coefficient, and dissociation pressure of the delta-phase mate… more
Date: July 11, 1957
Creator: Keller, D. L.
Partner: UNT Libraries Government Documents Department
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