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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.
Tyler R. Steiner, Emily N. Hutchins, Richard H. Howard
Nuclear Technology | Volume 208 | Number 1 | January 2022 | Pages 100-114
Technical Paper | doi.org/10.1080/00295450.2021.1879582
Articles are hosted by Taylor and Francis Online.
Nuclear thermal propulsion (NTP) demonstrated a reported technology readiness level of 5 during the work performed in the 1950s–1970s under the Rover program. This level of capability was achieved through the design, construction, and use of 22 experimental ground tests. These experiments served as testbeds for designs, materials, and instrumentation at prototypical NTP conditions. To continue the investigation into NTP system materials, components, and fuels, a modern experimental testbed has been designed and implemented. A steady-state, high-temperature, subscale, in-pile testbed has been developed to continue this investigation. The In-Pile Experiment Set Apparatus (INSET) has demonstrated that it can be used to test samples under two NTP prototypical environmental factors: temperature and neutron fluence. The demonstration using The Ohio State University Research Reactor is presented here. This demonstration required INSET to maintain a thermal environment below 1070 K for 15 min during a 5-h irradiation to achieve a neutron fluence around 1017 n/cm2.