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Meeting MS&T22: Materials Science & Technology
Symposium Progressive Solutions to Improve Corrosion Resistance of Nuclear Waste Storage Materials
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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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