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About this Symposium

Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Metallic Fuels - Design, Fabrication, and Characterization
Sponsorship TMS Structural Materials Division
TMS: Nuclear Materials Committee
Organizer(s) Ericmoore E. Jossou, Massachusetts Institute of Technology
Linu Malakkal, Idaho National Laboratory
Marat Khafizov, Ohio State University
Lingfeng He, North Carolina State University
Nana Ofori-Opoku, McMaster University
Anil Prasad, Canadian Nuclear Laboratories
Yongfeng Zhang, University of Wisconsin
Walter G. Luscher, Pacific Northwest National Laboratory
Scope This symposium will focus on the theme of metallic nuclear fuel design and fabrication. This area has significantly evolved in the last decade, due to advancements in fabrication hardware, computational approaches, and cutting-edge characterization techniques, from electron and X-ray sources at large-scale user facilities and benchtop setups.

Specifically, here we will examine the intricate correlations between structure-property-performance of various fuel forms with special emphasis on metallic fuels which are a product of both traditional and novel, innovative fabrication techniques. A particular emphasis will be placed on the fundamental insights into physical and chemical phenomena, making possible progress in characterization and computational methodologies across multiple length and time scales. We welcome contributions on a wide array of topics, which include but are not limited to:

  • Atomic-scale and experimental investigation of defects behavior and chemical segregation
  • Fuel materials microstructure modelling and analysis
  • Swelling and fission gas release in metallic fuels
  • Fuel-Cladding chemical interaction in metallic fuels
  • Separate effects irradiation testing of metallic fuel specimens
  • Emerging methods of fuel fabrication such as field-assisted sintering, additive manufacturing
  • Advances in in situ and operando monitoring of nuclear fuel fabrication and characterization
  • Machine learning assisted fabrication of advanced nuclear fuels
  • Testing and licensing of new nuclear fuel forms
  • Metallic fuel performance modeling under normal operating and accident scenarios
Abstracts Due 07/29/2025
Proceedings Plan Planned:

PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE



Advancements in Metallic Fuel Development and Qualification: Materials Challenges
Advances in the Understanding of Fuel-Cladding Chemical Interaction from FFTF MFF HT9 Clad U-Zr Metal Fuels
An Innovative Technique for Rapid Elemental and Isotopic Characterization of Nuclear Fuels
Analysis of Higher Burnup Sodium Free Annular U-10Zr Fuel
Assessing Thermal Conductivity in U-Zr Fuels: A Comparison of Modeling and Experimental Results
Atomic Mobility Assessments in the U-C-X Ternary Systems
Capturing fission products in metallic fuels using nanostructured interfaces
Comparison of FAST and Historical Irradiation Testing of U-Zr Fuels
Component Assembly and Fuel Fabrication for the IMPACT Advanced Test Reactor Irradiation Experiment
Compositional Effects on Phonon Dispersion and Lifetimes of UxTh1-xO2 using Inelastic X-Ray Scattering
Database-Driven Validation of BISON Metallic Fuel Performance Models for Sodium-Cooled Fast Reactors
Effects of ZrN coating and heat treatment on U-Mo dispersion fuel systems under irradiation
Fabrication and Properties of Metal Fuels with Controlled Porosities by Spark Plasma Sintering
Faulted and Perfect Loop Evolution with Dose and Temperature in Proton Irradiated Uranium Mononitride (UN)
First-Principles Assessment of Thermal Conductivity, in UCO TRISO Fuel with Varying Carbon Stoichiometry
First-Principles Evaluation of Heat Capacity in Disordered Uranium Oxycarbide Phases for TRISO Fuel Application
High-Resolution Characterization of U-Zr Metallic Fuel for Elucidating Precipitation and Fission Products Distribution Using Atom Probe Tomography
Influence of Heterogeneous Microstructures and Large Deformation on Blister Formation in Monolithic U–Mo Nuclear Fuels
Interactions between U-10Mo fuel with a burnable matrix
Investigating Phonon Transport in Uranium Nitride Using Neutron scattering
Investigating the structural and chemical properties in the oxidation of U-Th MOx fuel
Metal Fuels Opportunities Beyond Sodium Fast Reactors
Microalloying Metallic Fuels for Tracking and Traceability
Microstructural Investigation into Two Variants of Fuel-Cladding Chemical Interaction Observed in an Irradiated HT-9 Clad U-10Zr Metallic Fuel
Microstructure Analysis of Uranium-Molybdenum Fuel Alloy from Accelerated Irradiation at Various Temperatures
Novel Phase Identification and Characterization: Experimental insights in The U-Tc Binary System for Metallic Fuel Modeling
Scaling Irradiation Behaviors: Examining Steady-State Swelling, Redistribution, and Fission Gas Release in Larger Diameter U-Zr Fuel Pins
Site-specific porosity and high temperature behavior of U-10Zr fuel
Smaller and faster: conventional vs. nanocalorimetry techniques for determining thermophysical properties of nuclear fuels
Thermal Expansion and Neutron Cross-section of U-Mo fuel to 1000C
Thermal transport of uranium nitride (UN) after irradiation
Thermodynamic and Kinetic Pathways of Impurity-Induced Degradation in U-Ti-Nb-Mo-C Alloys
U-Zr Alloy Properties Review and Applicability to Lightbridge Corporation Fuel Performance Activities


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