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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.
Elif Ahsen Baştuğ, Hasan Oğul, Fatih Bulut, Ferdi Akman
Nuclear Technology | Volume 212 | Number 9 | September 2026 | Pages 2456-2471
Research Article | doi.org/10.1080/00295450.2025.2521960
Articles are hosted by Taylor and Francis Online.
In this study, acrylonitrile butadiene styrene (ABS) polymer composites reinforced with different weight fractions of MoS₂ and CaWO₄ were fabricated and investigated for their gamma and neutron shielding capabilities through both experimental and simulation-based approaches. Gamma-ray attenuation measurements were conducted using a NaI(Tl) detector system, while GEANT4 and FLUKA Monte Carlo codes were employed to simulate both gamma and neutron shielding performance. Additionally, theoretical values of mass attenuation coefficients (MACs) were calculated using EpiXS software.
Scanning electron microscopy analysis revealed a homogeneous dispersion of CaWO₄ and MoS₂ particles within the ABS matrix, although some agglomeration was observed at higher loadings. The results demonstrated that MS-3 and CW-3 exhibited superior gamma radiation shielding performance, with a MAC increase of approximately three times compared to ABS-0 at 59.5 keV. Notably, the MS-3 and CW-3 samples exhibited enhanced gamma attenuation, especially in the low-energy range.
Simulations also confirmed enhanced neutron shielding efficiency, particularly against thermal neutrons. In addition, the Monte Carlo simulations revealed that CW-3 generated the lowest levels of secondary gamma and neutron radiation, enhancing its overall shielding efficiency. For thermal neutrons, the CW-3 sample transmitted only ~8% of neutrons and produced 346 933 secondary photons. These findings highlight the potential of the developed composites as advanced materials for radiation protection in nuclear energy systems, medical facilities, and aerospace engineering.
