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August 24–27, 2026
Dallas, TX|Hilton Anatole
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Front-end nuclear fuel supply cooperation: Turning allied interdependence into strategic advantage
The global nuclear revival, which is fueled by unprecedented demand for firm, affordable, dispatchable power for artificial intelligence and data center build-out, energy security imperatives, and climate commitments, has exposed a structural reality of the Western fuel cycle: No single allied nation currently possesses the full suite of front-end capabilities. From mining through conversion, enrichment, fabrication, and the emerging deconversion and metallization steps required for reactor fuels, capability is distributed across Canada, France, Japan, the United Kingdom, and the United States (collectively, the “Sapporo Five”), as well as a small group of close partners.
Harry M. Ferrari
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 503-512
Technical Paper | doi.org/10.13182/NSE63-A18440
Articles are hosted by Taylor and Francis Online.
The mechanism and kinetics of nitrogen release from UO2 pellets containing high nitrogen impurities have been investigated at elevated temperatures. A combination of metallographic and x-ray analyses showed that nitrogen present in the UO2 exists as a second phase in the form of uranium nitrides. The kinetics of nitrogen release were measured at temperatures of 1000, 1200, 1400, and 1600°C and the mechanism of release was determined to be controlled by the diffusion of nitrogen through the UO2 lattice. The variation in nitrogen pressure upon heating a UO2 fuel element to elevated temperatures was studied. The data showed that a reversible equilibrium pressure-temperature relationship did not exist between the nitrides in the UO2 and the nitrogen gas above it as occurs with pure uranium nitrides. The quantity of nitrogen which will be released in a UO2 fuel element is determined by the kinetics of diffusion of nitrogen through the UO2 lattice and may be computed for any given fuel element design utilizing a diffusion model similar to one used for computing release of fission gases.