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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.
Ming Zhi Huang, Chong Zhou, Pu Yang, Wei Shi Wan, Zuo Kang Lin, Ye Dai
Nuclear Technology | Volume 209 | Number 1 | January 2023 | Pages 15-36
Technical Paper | doi.org/10.1080/00295450.2022.2096390
Articles are hosted by Taylor and Francis Online.
The existing thermal neutron molten salt reactor design has a complicated online processing system that has many technical difficulties. A thorium-based molten salt fast energy amplifier (TMSFEA) driven by a proton accelerator can operate stably for nearly 40 years at a rated thermal power of 300 MW without online processing. In order to simplify the core structure of TMSFEA, the core design is based on a hollow and moderator-free cylindrical geometry. The molten salt in the core serves as both fuel salt and spallation target. In this paper, based on the previous TMSFEA core neutron physics design, the core thermal-hydraulic design principles of TMSFEA are proposed, and a detailed core design with specific core structures as well as three-dimensional core thermal-hydraulic performance are obtained. Through computational fluid dynamics steady-state analysis, the arrangement of the core inlet and outlet and the shape of the core sidewall are optimized. Suitable distribution plates and skirt plates are proposed, and two corresponding lower plenum structures are designed to improve the flow field in the core. This study provides TMSFEA with core structures that meet the thermal-hydraulic design principles and also provides ideas for similar hollow reactor core designs.