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Meeting 2023 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications II
Presentation Title Microstructure and Thermophysical Property Characterization of U-ZrHx Fuel Fabricated by Powder Metallurgy
Author(s) Tyler Scott Smith, Caitlin Taylor, Michael Hahn, Erik Luther, Thomas Nizolek, Aditya Shivprasad
On-Site Speaker (Planned) Tyler Scott Smith
Abstract Scope Uranium-zirconium hydride (U-ZrHx) fuel is under consideration for microreactor applications. This type of fuel combines both fuel and moderator into a single material, and has proven to be a useful fuel type for TRIGA reactors. However, the ability to retain hydrogen and mitigate swelling at elevated temperatures and burnup becomes essential for fuel success in these applications. LANL has developed a powder metallurgy method for fabricating high density U-ZrHx fuel pellets. As-fabricated pellets were characterized using x-ray diffraction, microscopy, and thermophysical property measurements. This talk will overview these results and specifically address the thermal expansion, thermal conductivity, thermal diffusivity, and hydrogen retention of this fuel type at elevated temperatures.
Proceedings Inclusion? Planned:
Keywords Powder Materials, Nuclear Materials, Other

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

An Innovative Additive Manufacturing Route for Metal Matrix Composites for Nuclear Applications
Characterization of Defects Generated from Thermal Stresses in SiC/SiC Composites
Characterization of the Effects of Intermediate Temperature Neutron Irradiation on Model Fe-Cr Alloys
Correlating Heterogeneous Pore Distribution with Stochastic Fracture in the Pyrocarbon Buffer Layer in TRISO Fuel Particles
Development and Additive Manufacturing of ODS IN-718 Alloys for Nuclear Applications
Development and Evaluation of Dual-purpose Coating to SiC/SiC Composite Accident-tolerant Fuel Cladding for Light Water Reactors
Development of SiCf/SiC Composite Materials for Fusion Applications
Effect of Copper Fiber in RAFM Steel Composite on Improving the Thermal Conductivity
Effect of Hot Rolling and High Temperature Annealing on the Microstructure and Mechanical Properties of Hot-rolled 90W7Ni3Fe WHA
Effect of Interfacial Features on the Strengthening Behavior of B4C/Al Composites
ENHANCED Shield: A Critical Materials Technology Enabling Compact Superconducting Tokamaks
Ion Beam Synthesis of Nano-Oxides in FeCr: Towards an Understanding of Precipitation in Oxide Dispersion Strengthened Steels
Irradiation Effects in the Composite Phases of Graphite and Carbon-Based Materials
Is there Residual Stress in Tungsten Fiber Reinforced Tungsten Composites
Mechanistic Understanding of Hydrothermal Corrosion of SiC Under Irradiation
Microstructure and Mechanical Behavior of Cr Coatings for Mitigating Hydrothermal Corrosion of SiC-SiCf Fuel Cladding
Microstructure and Thermophysical Property Characterization of U-ZrHx Fuel Fabricated by Powder Metallurgy
Next-generation Nuclear Grade Composite Components
Nuclear Graphite as a Core Composite Material
Oxidation Effects on the Microstructure of Nuclear Graphite
Oxidation Response of Irradiated and Unirradiated TRISO Fuel
Progress in the Development of Tungsten Fibre-reinforced Copper Composites for Heat Sink Applications in Plasma-facing Components
Recent Progress in the Development of Tungsten Fibre-reinforced Tungsten Composite
Role and Structure of HTGR Matrix Material
Ruthenium and Silver Diffusion in Nuclear Graphite
Status Update on Framatome PROtect ATF Solutions: Cr-coated M5Framatome and SiCf/SiC Cladding Designs
Stress Rupture of SiC/SiC Composite Tubes Under High-temperature Steam: Implications for Resistance to Light Water Reactor Accident
Thermal Properties of Dispersoid-strengthened Tungsten Alloys for Fusion Applications
W2C-reinforced Tungsten: A Promising Candidate for EU DEMO Divertor Material

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