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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.
Laure Carénini, Florian Fichot
Nuclear Technology | Volume 212 | Number 8 | August 2026 | Pages 2077-2100
Research Article | doi.org/10.1080/00295450.2025.2525715
Articles are hosted by Taylor and Francis Online.
In this paper, the impact of the uncertainties associated with the modeling of core degradation in the production of hydrogen in the vessel (total mass and mass production rate) is evaluated for a generic PWR1300MWe reactor design. Different studies involving propagation of physical and modeling uncertainties were carried out with the ASTEC V3 severe accident code, following a dedicated step-by-step approach to allow a better analysis of the results. With a focus on the hydrogen generation during core degradation, the selection of a relevant scenario is done using adapted boundary conditions starting from the core dewatering. Several studies are performed, each focusing on a different physical phenomenon or a group of related phenomena, and allow detailed understanding of the code response. In the end, the propagation of all uncertain parameters previously identified is done to evaluate the global hydrogen variation. A total of 37 uncertain parameters are defined, and 600 calculations performed (400 for the preliminary studies and 200 for the final one combining all physical uncertainties). For the selected scenario (small break scenario of 2 in.), a variation of less than ±20% is obtained for a total mass of H2 of 700 kg calculated with the reference modeling. The analysis carried out demonstrated that the uncertainties associated with the loss of geometry of the rods are responsible for the most significant variations and for the maximum values in terms of total H2 produced. In addition, compensating effects between claddings and corium oxidation are identified during the transient evolution and discussed.