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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 Neutron Diffraction Residual Stress Characterization of Stainless Steel Produced by Wire Arc Direct Energy Deposition
Author(s) Wei Tang, Ke An, Dunji Yu, Dominic Giuliano, Oscar Martinez, Andrzej Nycz, Maxim Gussev, Luke Meyer, Derek Vaughan
On-Site Speaker (Planned) Wei Tang
Abstract Scope Additive Manufacturing (AM) produces components following 3D model data, usually by building up materials pass-by-pass and layer-upon-layer. Wire arc direct energy deposition (WA-DED) is an AM technique that is suitable for large and complex structures with flexible printing characteristics and high deposition rates, which yields manufacturing cost savings. Because of the welding processes, residual stresses are expected in WA-DED manufactured products. One degradation concern of spent nuclear fuel (SNF) canisters is chloride-induced stress corrosion cracking (CISCC). High welding tensile residual stress plays an important role in triggering CISCC. In this study, components simulating SNF canisters were produced by WA-DED AM and traditional technologies. Residual stresses in manufactured parts were measured and characterized by neutron diffraction. Furthermore, component microstructures were characterized, and mechanical properties were evaluated. Results showed comparable maximum tensile residual stress in both products, and microstructure and mechanical properties were compared between the two products. This is a technical presentation that does not take into account contractual limitations or obligations under the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (Standard Contract) (10 CFR Part 961). To the extent discussions or recommendations in this presentation conflict with the provisions of the Standard Contract, the Standard Contract governs the obligations of the parties, and this presentation in no manner supersedes, overrides, or amends the Standard Contract. This presentation reflects technical work which could support future decision making by the U.S. Department of Energy (DOE or Department). No inferences should be drawn from this presentation regarding future actions by DOE, which are limited both by the terms of the Standard Contract and a lack of Congressional appropriations for the Department to fulfill its obligations under the Nuclear Waste Policy Act including licensing and construction of a spent nuclear fuel repository. This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doepublic-access-plan).

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Neutron Diffraction Residual Stress Characterization of Stainless Steel Produced by Wire Arc Direct Energy Deposition
Physics-informed Machine Learning for Glass Property Predictions
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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