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Characterization of the Resistance of Alloy 22 to Stress Corrosion Cracking.

DE200515013493

Publication Date	2002
Personal Author	King, K. J.; Rebak, R. B.; Estill, J. C.
Page Count	20
Abstract	In its current design, the high-level nuclear waste containers include an external layer of Alloy 22. Since over their lifetime, the containers may be exposed to multi-ionic aqueous environments, a potential degradation mode of the outer layer could be environmentally assisted cracking (EAC). The objective of the current research was to characterize the effect of applied potential and temperature on the susceptibility of Alloy 22 to EAC in simulated concentrated water (SCW) using the slow strain rate test (SSRT). Results show that Alloy 22 may suffer EAC at applied potentials approximately 400 mV more anodic than the corrosion potential.
Keywords	Corrosion resistance Alloys Stress corrosion cracking High level radioactive wastes Containers Temperature effects Nickel based alloys Chromium Stainless steels Molybdenum Tungsten Iron Environmental tests Shielding Radiation Strain rate tests Water Localized corrosion Structural integrity
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Lawrence Livermore National Lab., CA.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200522

Characterization of the Resistance of Alloy 22 to Stress Corrosion Cracking.

Characterization of the Resistance of Alloy 22 to Stress Corrosion Cracking.
DE200515013493

Publication Date	2002
Personal Author	King, K. J.; Rebak, R. B.; Estill, J. C.
Page Count	20
Abstract	In its current design, the high-level nuclear waste containers include an external layer of Alloy 22. Since over their lifetime, the containers may be exposed to multi-ionic aqueous environments, a potential degradation mode of the outer layer could be environmentally assisted cracking (EAC). The objective of the current research was to characterize the effect of applied potential and temperature on the susceptibility of Alloy 22 to EAC in simulated concentrated water (SCW) using the slow strain rate test (SSRT). Results show that Alloy 22 may suffer EAC at applied potentials approximately 400 mV more anodic than the corrosion potential.
Keywords	Corrosion resistance Alloys Stress corrosion cracking High level radioactive wastes Containers Temperature effects Nickel based alloys Chromium Stainless steels Molybdenum Tungsten Iron Environmental tests Shielding Radiation Strain rate tests Water Localized corrosion Structural integrity
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Lawrence Livermore National Lab., CA.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200522