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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.
C. Ronchi, J. P. Hiernaut, R. Selfslag, G. J. Hyland
Nuclear Science and Engineering | Volume 113 | Number 1 | January 1993 | Pages 1-19
Technical Paper | doi.org/10.13182/NSE93-A23990
Articles are hosted by Taylor and Francis Online.
The heat capacity Cp of UO2 was measured in a laboratory experiment where sintered 0.5-to 1-mm-diam microspheres were heated by four tetrahedrally oriented laser beams in an inert-gas-filled autoclave at pressures up to ∼1000 bar. The sample, suspended by a tungsten needle, was heated to 8000 K during pulses of a few milliseconds duration. The experimental technique, the instrumentation, and the analytical method used to deduce Cp from the experimental pulse-heating curves are described. Between the melting point Tm and ∼4000 K, the heat capacity decreases to a value close to that given by the Neumann-Kopp rule for a triatomic, harmonic lattice, i.e., 9R. Near 5000 K, however, the heat capacity again increases, and it appears to saturate at a value ∼30% higher by 8000 K. The new results are compared with published Cp values for molten UO2 (and other relevant materials) and are briefly discussed in light of the established temperature dependence of Cp at T < Tm and the high-energy electronic structure of UO2.