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Meeting MS&T25: Materials Science & Technology
Symposium Metallic Nuclear Fuel Design, Fabrication and Characterization
Presentation Title Nitinol as Surrogate for Laser Additive Manufacturing of Uranium-10 Zirconium Metallic Nuclear Fuel
Author(s) Abhi Ghosh, Reza Esmaeilizadeh, Anil Prasad, Gregory Hamilton, Ike Dimayuga
On-Site Speaker (Planned) Anil Prasad
Abstract Scope Fabrication of Uranium-Zirconium (U-Zr) metallic fuels for Generation IV Sodium Fast Reactors via advanced manufacturing processes like laser-based metal additive manufacturing (AM) could allow for performance enhancements concerning swelling control and gas release, higher burn-up capacity, and better heat transfer efficiency during reactor operations. The laser AM fabrication of U-10wt%Zr (U-10Zr) involves complex solidification and phase transformations under rapid cooling conditions, which could result in fabrication-related defects such as cracks, distortions, and print failures. As a non-active precursor to active fabrication studies with U-10wt%Zr (U-10Zr), a near-equiatomic Nitinol is selected as a viable surrogate for U-10Zr to represent key solidification features during the fuel fabrication, including similar phase and crystallographic transformations, as well as the analogous metastable and secondary phases formed during rapid solidification. Ultimately, with comparable melting and thermal properties, Nitinol could potentially serve as a viable proxy to assess the printability of U-10Zr with LP-DED.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advanced Characterization of Pu Oxidation with S/TEM
Characterization of High Uranium Density Compositionally Complex Refractory Alloys
Exploring the Complex Interplay Between Phases, Porosity, and Thermal Properties in Metallic Fuels
High Temperature Structures, Oxidation, and Thermodynamics of Uranium Fuels
Impact of Dislocation Loops on the Thermal Transport in Nuclear Fuels: A First-Principles Atomistic Approach
Metal Fuel Performance in Sodium Fast Reactors: Post-Irradiation Examination and Innovative Experiments
Mitigating FCCI in Metallic Fuels: Evaluating Cladding Liners Using Multiscale Modeling
Multi-scale modeling of wastage layer formation in metallic fuel cladding
Multiscale fuel performance modeling of U-Mo fuel for research reactors
Nitinol as Surrogate for Laser Additive Manufacturing of Uranium-10 Zirconium Metallic Nuclear Fuel
Perspectives on Accelerated Fuel Irradiation Testing in Uranium-Zirconium Alloys
Refractory Systems in Uranium-Containing Alloys for High Temperature Metallic Fuel
Thermal transport of uranium nitride (UN) after irradiation
Three-Dimensional Microstructural Evolution of Irradiated U-10Zr Nuclear Fuel Revealed by Synchrotron X-ray Micro-CT
Understanding grain refinement and gas bubble evolution in U-10Mo fuel using phase-field modeling
Volume fraction of porosity and distinct phases in irradiated FAST U-Zr fuel using manual point counting and automatic image analysis

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