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Meeting MS&T22: Materials Science & Technology
Symposium Progressive Solutions to Improve Corrosion Resistance of Nuclear Waste Storage Materials
Presentation Title Environmental Cracking Lifetime Prediction through the Development of Pitting and SCC Models for Nuclear Waste Storage Casks
Author(s) Sarah Blust, James T Burns
On-Site Speaker (Planned) Sarah Blust
Abstract Scope Used nuclear fuel (UNF) is currently stored across the US in passively cooled stainless steel dry storage canisters (DSC). Due to the design of the DSC, aerosols from the outside environment are able to deposit on the stainless-steel canisters. Over time the deposited aerosols will deliquesce on canisters to form concentrated salt brines resulting in localized corrosion, which when coupled with the high residual stress around welds can lead to stress corrosion cracking (SCC). The objective of this study is to create a model for the life-management of DSC, which will inform a framework to quantify and manage a risk-based ranking of storage sites. The specific goals of this work are to: (a) validate the maximum pit size model for DSC-relevant corrosion conditions (b) coupling the limiting pit size/Kondo approaches, (c) generate da/dt vs. K data and perform probabilistic FM predictions of SCC growth, and (d) validate the model predictions.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Designing Glasses for Nuclear Waste Immobilization with AI and ML
Diminished Diffusion in the Aged Hydrated Gels of Irradiated Borosilicate Glasses
Environmental Cracking Lifetime Prediction through the Development of Pitting and SCC Models for Nuclear Waste Storage Casks
From Preferential Bonding to Phase Separation in Boro-silicate Glasses
Microstructural Development and Chemical Durability of a Borosilicate Glass-ceramic Waste-form
Predicting the Long-term Durability of Nuclear Waste Immobilization Glasses using Machine Learning
SCC of Nuclear Waste Canisters: Mechanisms and Mitigation

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