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MS&T24: Materials Science & Technology
Symposium
Progressive Solutions to Improve the Corrosion Resistance of Nuclear Waste Storage Materials
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OTHER PAPERS PLANNED FOR THIS SYMPOSIUM
Neutron Diffraction Residual Stress Characterization of Stainless Steel Produced by Wire Arc Direct Energy Deposition
Polymer-Derived Ceramic Coatings for Nuclear Waste Storage Canister Corrosion Prevention
Quantitative Analysis of Hydrogen Interactions with UO2 Grain Boundaries Using Density Functional Theory
Structural Design of Borosilicate-Based Nuclear Waste Glasses
Structural Origin of the Passivation Effect Nuclear Waste Immobilization Glasses
Transition Metal Ions Induced Structural Rearrangements and Their Impact on Sulfur Solubility in Borosilicate-Based Model Nuclear Waste Glasses
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