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Understanding and Predicting Stress Corrosion Cracking of SNF Dry Storage Canisters

Proceedings of the International High-Level Radioactive Waste Management Conference, IHLRWM 2022, Embedded with the 2022 ANS Winter Meeting

Bryan, Charles R.; Knight, Andrew W.; Nation, Brendan L.; Katona, Ryan M.; Karasz, Erin K.; Montoya, T.J.; Brooks, Dusty M.; Porter, N.W.; Gilkey, Lindsay N.; Taylor, Jason M.; Schaller, Rebecca S.

Abstract not provided.

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TYPE Conference Paper YEAR 2022
OSTIScopus

Measuring the Residual Stress and Stress Corrosion Cracking Susceptibility of Additively Manufactured 316L by ASTM G36-94

Corrosion

Karasz, Erin K.; Taylor, Jason M.; Autenrieth, David M.; Reu, Phillip L.; Johnson, Kyle J.; Melia, Michael A.; Noell, Philip N.

Residual stress is a contributor to stress corrosion cracking (SCC) and a common byproduct of additive manufacturing (AM). Here the relationship between residual stress and SCC susceptibility in laser powder bed fusion AM 316L stainless steel was studied through immersion in saturated boiling magnesium chloride per ASTM G36-94. The residual stress was varied by changing the sample height for the as-built condition and additionally by heat treatments at 600°C, 800°C, and 1,200°C to control, and in some cases reduce, residual stress. In general, all samples in the as-built condition showed susceptibility to SCC with the thinner, lower residual stress samples showing shallower cracks and crack propagation occurring perpendicular to melt tracks due to local residual stress fields. The heat-treated samples showed a reduction in residual stress for the 800°C and 1,200°C samples. Both were free of cracks after >300 h of immersion in MgCl2, while the 600°C sample showed similar cracking to their as-built counterpart. Geometrically necessary dislocation (GND) density analysis indicates that the dislocation density may play a major role in the SCC susceptibility.

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TYPE Journal Article YEAR 2022
DOIOSTIScopus

SNF Interim Storage Canister Corrosion and Surface Environment Investigations (FY21 Status Report)

Bryan, Charles R.; Knight, Andrew W.; Nation, Brendan L.; Montoya, Timothy M.; Karasz, Erin K.; Katona, Ryan M.; Schaller, Rebecca S.

This progress report describes work performed during FY21 at Sandia National Laboratories (SNL) to assess the localized corrosion performance of canister materials used in the interim storage of spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. In FY21, modeling and experimental work was performed that further defined our understanding of the potential chemical and physical environment present on canister surfaces at both marine and inland sites. Research also evaluated the relationship between the environment and the rate, extent, and morphology of corrosion, as well as the corrosion processes that occur. Finally, crack growth rate testing under relevant environmental conditions was initiated.

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TYPE Other Report YEAR 2021
DOIOSTI
Results 26–44 of 44
Results 26–44 of 44