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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.
P. Goldschmidt, J. Quenon
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 311-319
Technical Paper | doi.org/10.13182/NSE70-A19992
Articles are hosted by Taylor and Francis Online.
A method of optimizing the fissile fuel distribution to obtain minimum critical mass for a fast breeder reactor of fixed power is presented. Constraints on the power density and on the fuel enrichment are considered. The reactor is described by one-group diffusion theory. The optimal trajectory in the phase space (flux-current) is found a priori using the Maximum Principle of Pontryagin. It is shown that in general, the optimum reactor has three distinct regions: a central constant-power-density region, a region of maximum fuel enrichment and an outer region of minimum enrichment corresponding to the blanket. The existence of this last region and its dimension depend on the outer boundary condition which can simulate the presence of an external reflector. The expressions obtained for the optimized dimensions of each region can be solved analytically and numerical results are given.