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Meeting MS&T24: Materials Science & Technology
Symposium Progressive Solutions to Improve the Corrosion Resistance of Nuclear Waste Storage Materials
Presentation Title Quantitative Analysis of Hydrogen Interactions with UO2 Grain Boundaries Using Density Functional Theory
Author(s) Rajat Goel, Ambar Kulkarni, Nir Goldman
On-Site Speaker (Planned) Rajat Goel
Abstract Scope Uranium degradation caused by hydrogen, resulting in the formation of the highly flammable and toxic uranium hydride (UH3), poses significant safety risks in the nuclear industry, particularly during fuel storage and waste management. Recent studies indicate that hydrogen diffusion through the grain boundaries (GBs) of the passivating uranium oxide (UO2) layer is a major factor in hydriding initiation. However, there is limited understanding of hydrogen interactions at these GBs, which is crucial for developing effective mitigation strategies. This talk will present the first step in addressing this challenge by elucidating the use of large-scale Density Functional Theory (DFT) to model UO2 grain boundaries and investigate their interactions with hydrogen atoms. Additionally, we highlight our future direction to simulate H diffusion near experimental and spacial scales.

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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