Conference Logo ProgramMaster Logo
Conference Tools for MS&T25: Materials Science & Technology
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools

About this Abstract

Meeting MS&T25: Materials Science & Technology
Symposium Metallic Nuclear Fuel Design, Fabrication and Characterization
Presentation Title Characterization of High Uranium Density Compositionally Complex Refractory Alloys
Author(s) Malachi Nelson, Boone Beausoleil, James Zillinger, Brian Newell, George Evans
On-Site Speaker (Planned) Malachi Nelson
Abstract Scope Metallic fuels provide attractive properties such as high fuel density, excellent thermal conductivity, and low heat capacity. However, conventional metallic fuels also exhibit significant swelling behavior which can be problematic for advanced geometries, have meta-stable phases, and phase segregation. This work investigates uranium compositionally complex alloys (UCCA) as a potential high temperature metallic fuel with BCC phase stability to inhibit swelling, maintain adequate thermal properties, and increase acceptable temperature ranges for use. RMPEA samples are fabricated with and without uranium and the resulting alloys are characterized using electron dispersive spectroscopy and X-ray diffraction to evaluate phase formation and microstructure. Differential scanning calorimetry is used to measure the thermodynamic properties of these novel alloys including heat capacity, transition temperatures, and latent heat. Samples are annealed at temperatures informed by the calorimetry measurements and resulting microstructures are also characterized for phase stability.

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

Questions about ProgramMaster? Contact programming@programmaster.org | TMS Privacy Policy | Accessibility Statement