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Meeting MS&T23: Materials Science & Technology
Symposium Progressive Solutions to Improve Corrosion Resistance of Nuclear Waste Storage Materials
Sponsorship TMS: Energy Committee
TMS: Nuclear Materials Committee
Organizer(s) Madeleine K. Jordache, Stevens Institute of Technology
Gary R. Pickrell, Virginia Tech
Daniel R. Cassar, Brazilian Center for Research in Energy and Materials (CNPEM)
Scope Increased long-term corrosion resistance of the nuclear waste storage materials is critical to restrict the escape of radioactive products into the environment.

This symposium will enclose two major research topics:

1) Development of environmental safe nuclear storage materials through new, non environment contamination glass processing techniques, and solutions for long-term stable material systems at the geological repository.

2) Improvement of corrosion resistance of nuclear waste storage materials currently considered.

This symposium will give researchers worldwide an opportunity to discuss developments in the specific characterization techniques, including Neutron Diffraction, High-Energy X-ray Diffraction, Extended X-ray absorption fine structure (EXAFS), Nuclear Magnetic Resonance (NMR) and Raman Spectroscopy.

Further, the symposium will attract outstanding scientists to present Molecular Dynamic (MD) simulations and experiments to understand aqueous glass corrosion and effects on its structure, stability and mechanical properties and Machine Learning (ML) to predict long-term durability and to design glasses and glass-ceramics for long-term nuclear waste storage.

Modeling and experiments to understand the corrosion and stress corrosion cracking (scc) resistance of steel canisters used for temporary storage, with means to mitigate and repair are welcome. Work for corrosion of steel canisters to be used to store glass hosting nuclear waste for long term storage at the geological repository is of particular interest.

Thermodynamic views into the nuclear waste glass and steel corrosion are looked for.

Experimental and modeling approaches to study and propose improvement in toughness of glass and glass-ceramics and glass and glass-ceramics canisters to host nuclear waste are invited.

Abstracts Due 05/08/2023

An Integrated Data-driven and Physics-driven Approach Towards Discovering Optimal Nuclear Waste Immobilization Glass
Chloride-induced Stress Corrosion Crack in Spent Nuclear Fuel Canisters: Understanding and Mitigating
Evaluating the Sensitivities of an Environmental Cracking LEFM-based Model for Use in Realistic Lifetime Predictions of Nuclear Waste Storage Casks
Gel Layer Structures and Properties of Silicate Glasses: Understanding the Corrosion of Glasses for Nuclear Waste Disposal
SiON Protective Coatings for U-shaped Stainless Steel
Structural Descriptors Controlling Sulfur Solubility in Borosilicate Glasses
Topological Model of the Dissolution Kinetics of Borosilicate Glasses

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