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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.
M. Michelini
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 116-126
Technical paper | doi.org/10.13182/NSE72-A28424
Articles are hosted by Taylor and Francis Online.
In the study of the possibilities of improving the accuracy of diffusion calculations, a point-by-point formulation has been established of the diffusion coefficient DK(x,y) most appropriate to heterogeneous systems comprised of low absorbing media, that is a formulation which contains all the information obtainable from such a system. Since the actual size of each medium is taken into account, this formulation can predict the proper diffusion coefficients even within cavities. In this work three coefficients, Dx, Dy, and Dz, of anisotropic diffusion are derived for any rectangular elementary region imbedded in a generalized X, Y geometry. They enable us to perform more accurate diffusion calculations in all cases where classical diffusion can be used. In addition, anisotropic diffusion allows the study of nonhomogenized cavities. Finally, numerical calculations confirm that anisotropic diffusion is very suitable in many pròblems.