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2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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Center for Used Fuel Research: Building confidence in storage and transport
Used nuclear fuel storage and transportation have reached a critical juncture.
Dozens of utilities need reliable data on how used nuclear fuel performs in dry storage casks and canisters to extend regulatory licenses at sites across the United States. Likewise, the Department of Energy expects to take ownership of the used nuclear fuel—termed “spent nuclear fuel” in the laws and regulations governing its stewardship—and transfer it to one or more federal staging facilities for management and disposition.
Meanwhile, dozens of reactor companies are testing prototypes of advanced reactors and advanced reactor fuels. Eventually, regulators and industry must also verify the safety and security of storage methods for these advanced fuel types.
To help address these challenges, the DOE established the Center for Used Fuel Research (CUFR) in January 2026 for work related to the long-term storage and transport of used nuclear fuel.
D. A. Huston, A. Prasad, N. Kotsios, A. Bergeron, F. Kelly, E. C. Corcoran
Nuclear Technology | Volume 212 | Number 2 | February 2026 | Pages 395-409
Regular Review Article | doi.org/10.1080/00295450.2025.2472094
Articles are hosted by Taylor and Francis Online.
Instrumented fuel pellets offer the potential to be used for the real-time measurement of fuel properties within emerging nuclear reactor designs. The use of three-dimensional (3D) printed nuclear fuel pellets is one approach to accommodate instrumentation. The 3D printing of nuclear materials requires that a printable feedstock material be developed for use with a specific additive manufacturing technology. In the present work, an iterative design process was used to formulate a filament containing yttria-stabilized zirconia, as a surrogate for uranium dioxide, that is suitable for use with fused filament fabrication 3D printers.
The components of the filament and their amounts, the printing parameters, and the debinding process were varied to produce an optimized printing procedure. A final five-component formulation containing 50.0 ± 0.1 vol % organic material was developed. With this formulation, the requirement to print to a 16-mm wall thickness, consistent with CANDU pellet dimensions rather than the maximum of 4 mm reported previously, resulted in numerous production failures. Ultimately, the manipulation of specific printer parameters to form microchannels within the pellet during printing resulted in pellets consistent with the target criteria. In the final set of eight pellets, seven pellets met the density criterion of 95% theoretical density, with an average density of 96.2 ± 1.0% of theoretical density.