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Meeting MS&T22: Materials Science & Technology
Symposium Progressive Solutions to Improve Corrosion Resistance of Nuclear Waste Storage Materials
Presentation Title Designing Glasses for Nuclear Waste Immobilization with AI and ML
Author(s) N M Anoop Krishnan
On-Site Speaker (Planned) N M Anoop Krishnan
Abstract Scope Despite the use of glasses for more than 2000 years, the composition-structure-property relationships in these materials remain elusive. Here, we discuss how the improved glasses can be designed for nuclear waste immobilization. Specifically, we focus on three aspects namely, (i) ML-based property prediction, (ii) physics-informed ML for viscosity prediction, and (iii) information extraction from the literature. First, we discuss how ML models can be used for predicting electrical, and mechanical properties. Second, we show the use of physics-informed ML for predicting viscosity, which combines the MYEGA equation with ML to predict the viscosity of unknown glasses. Further, the ML models are used as surrogates along with constrained optimization to identify new potential glass compositions. Finally, we discuss how natural language processing can be used to extract information from the literature regarding nuclear waste immobilization, which can be effectively used for accelerating the discovery of new glasses.

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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