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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.
Irfan Ibrahim, Megan Harkema, Steven Krahn, Hangbok Choi, John Bolin, Eric Thornsbury
Nuclear Technology | Volume 212 | Number 2 | February 2026 | Pages 253-276
Review Article | doi.org/10.1080/00295450.2025.2472573
Articles are hosted by Taylor and Francis Online.
One of the few gas-cooled fast reactor (GFR) concepts being investigated within the United States is the General Atomics Electromagnetic Systems’ fast modular reactor (FMR). As a first step in developing the safety case for the FMR, a comprehensive range of potential accident initiators should be identified. To characterize the breadth of the initiators that could occur in GFRs, a literature review was performed to identify preliminary initiating events (PIEs) relevant to GFRs, with an emphasis on those initiators relevant to the FMR design.
For the review, PIEs were defined as deviations from normal operating conditions that could lead to undesired plant states and represent the beginning of potential accident sequences. The literature review included events meeting the definition of PIEs that had previously been identified and analyzed for GFRs, high-temperature gas-cooled reactors, very high–temperature reactors, and commercial gas-cooled reactors.
A total of 124 references were evaluated and 549 unique PIEs were identified. The most frequently assessed PIEs in the literature were categorized as loss-of-coolant accidents (LOCAs) and flow-related transients. Repeated treatment of these accident types, especially LOCAs, within the literature emphasizes the importance, and due analysis, of potential depressurization events in a GFR’s safety case, since such events can have potentially important downstream effects in some designs. Less emphasis was observed on initiating events associated with helium purification systems and external events, which also have the potential to challenge plant safety, and therefore may require further evaluation to support safety case development for GFRs, and the FMR specifically.