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The busyness of the nuclear fuel supply chain
Ken Petersenpresident@ans.org
With all that is happening in the industry these days, the nuclear fuel supply chain is still a hot topic. The Russian assault in Ukraine continues to upend the “where” and “how” of attaining nuclear fuel—and it has also motivated U.S. legislators to act.
Two years into the Russian war with Ukraine, things are different. The Inflation Reduction Act was passed in 2022, authorizing $700 million in funding to support production of high-assay low-enriched uranium in the United States. Meanwhile, the Department of Energy this January issued a $500 million request for proposals to stimulate new HALEU production. The Emergency National Security Supplemental Appropriations Act of 2024 includes $2.7 billion in funding for new uranium enrichment production. This funding was diverted from the Civil Nuclear Credits program and will only be released if there is a ban on importing Russian uranium into the United States—which could happen by the time this column is published, as legislation that bans Russian uranium has passed the House as of this writing and is headed for the Senate. Also being considered is legislation that would sanction Russian uranium. Alternatively, the Biden-Harris administration may choose to ban Russian uranium without legislation in order to obtain access to the $2.7 billion in funding.
Paul A. Demkowicz, James L. Jerden, Jr., James C. Cunnane, Noriko Shibuya, Ronald Baney, James Tulenko
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 157-170
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3522
Articles are hosted by Taylor and Francis Online.
The aqueous dissolution of irradiated and unirradiated uranium-thorium dioxide, (U,Th)O2, fuel pellets in Yucca Mountain well water has been investigated. Whole and crushed pellets were reacted at 25 and 90°C for periods of up to 195 days. The fuel dissolution was measured by analyzing the concentrations of soluble uranium, thorium, and important fission products (137Cs, 99Tc, 237Np, 239Pu, 240Pu, and 241Am) in the well water. The surface-area-normalized fractional uranium release rates for unirradiated crushed uranium dioxide (UO2) pellets were 10 to 40 times higher than the values for (U,Th)O2 fuel. Similarly, the dissolution rates of irradiated (U,Th)O2 pellets with compositions ranging from 2.0 to 5.2% UO2 were at least two orders of magnitude lower than reported literature values for pure UO2. These results demonstrate an advantage of (U,Th)O2 over UO2 in terms of matrix dissolution in groundwater and suggest that (U,Th)O2 fuel is a more stable long-term waste form than conventional UO2 fuel.
