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Constant Load SCC Initiation Response of Alloy 22 (UNS N06022), Titanium Grade 7 and Stainless Steels at 105 degree C.

DE2004808012

Publication Date	2004
Personal Author	Young, L. M.; Catlin, G. M.; Andresen, P. L.
Page Count	20
Abstract	This paper provides an update on research addressing the effects of material condition and applied stress on stress corrosion cracking (SCC) in waste package and drip shield materials for the Yucca Mountain Project. Time-to-failure experiments are being performed on smooth bar tensile specimens in a hot, concentrated, mixed-salt solution chosen to simulate concentrated Yucca Mountain water. The effects of applied stress, welding, surface finish, shot peening, cold work, crevicing, and aging treatment are being investigated for Alloy 22 (UNS N06022). Aging treatments were designed to produce topologically close-packed phases (TCP) and long-range ordering (LRO) and are under investigation as worse-case scenarios for possible microstructures in Alloy 22 (UNS N06022). Titanium Grade 7 and 3 16NG stainless steel are included in the matrix, as they are identified for drip shield and waste package components, respectively. Sensitized 304SS specimens are included in the test matrix to provide benchmark data. This research complements high-resolution crack-growth-rate experiments currently being performed in a parallel research project.
Keywords	Stress corrosion cracking Alloys Titanium Stainless steels Packaging Radioactive waste storage Stresses Materials tests Yucca Mountain Welding Surface finishing Shot peening Cold working Aging Failure Corrosion Crevice corrosion Drip shields
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	General Electric Co., Schenectady, NY. Global Research Center.; Department of Energy, Washington, DC.; Framatome, Las Vegas, NV.
Supplemental Notes	Prepared in cooperation with Framatome, Las Vegas, NV. Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200508

Constant Load SCC Initiation Response of Alloy 22 (UNS N06022), Titanium Grade 7 and Stainless Steels at 105 degree C.

Constant Load SCC Initiation Response of Alloy 22 (UNS N06022), Titanium Grade 7 and Stainless Steels at 105 degree C.
DE2004808012

Publication Date	2004
Personal Author	Young, L. M.; Catlin, G. M.; Andresen, P. L.
Page Count	20
Abstract	This paper provides an update on research addressing the effects of material condition and applied stress on stress corrosion cracking (SCC) in waste package and drip shield materials for the Yucca Mountain Project. Time-to-failure experiments are being performed on smooth bar tensile specimens in a hot, concentrated, mixed-salt solution chosen to simulate concentrated Yucca Mountain water. The effects of applied stress, welding, surface finish, shot peening, cold work, crevicing, and aging treatment are being investigated for Alloy 22 (UNS N06022). Aging treatments were designed to produce topologically close-packed phases (TCP) and long-range ordering (LRO) and are under investigation as worse-case scenarios for possible microstructures in Alloy 22 (UNS N06022). Titanium Grade 7 and 3 16NG stainless steel are included in the matrix, as they are identified for drip shield and waste package components, respectively. Sensitized 304SS specimens are included in the test matrix to provide benchmark data. This research complements high-resolution crack-growth-rate experiments currently being performed in a parallel research project.
Keywords	Stress corrosion cracking Alloys Titanium Stainless steels Packaging Radioactive waste storage Stresses Materials tests Yucca Mountain Welding Surface finishing Shot peening Cold working Aging Failure Corrosion Crevice corrosion Drip shields
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	General Electric Co., Schenectady, NY. Global Research Center.; Department of Energy, Washington, DC.; Framatome, Las Vegas, NV.
Supplemental Notes	Prepared in cooperation with Framatome, Las Vegas, NV. Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200508