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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.
Shigeki Shiba
Nuclear Technology | Volume 212 | Number 6 | June 2026 | Pages 1623-1639
Regular Note | doi.org/10.1080/00295450.2025.2502262
Articles are hosted by Taylor and Francis Online.
The fifth version of the Japanese Evaluated Nuclear Data Library (JENDL-5) was released in December 2021. It is essential to validate JENDL-5 using the reactor core analysis data of light water reactors and to evaluate the performance of JENDL-5 in comparison with other major nuclear data libraries, namely, JENDL-4.0, ENDF/B-VIII.0, and ENDF/B-VII.1. In this paper, reactor core analyses of Tihange-2, which is a three-loop 900-MW(electric) Framatome pressurized water reactor, were performed using CASMO5/SIMULATE5. The results indicated that the radial power distributions were accurately simulated using JENDL-5, but discrepancies in the critical boron concentration during cycle burnups were observed. The main cause of these discrepancies was found to be low reactivity caused by the 239Pu reaction cross section in JENDL-5. Accordingly, further validation and code updates are expected in applying the library to core analyses of light water reactors.