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2026 Nuclear Energy Conference & Expo (NECX)
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.
Edward W. Larsen
Nuclear Science and Engineering | Volume 60 | Number 4 | August 1976 | Pages 357-368
Technical Paper | doi.org/10.13182/NSE76-A26897
Articles are hosted by Taylor and Francis Online.
We construct an asymptotic solution of the neutron transport equation in a large heterogeneous medium using a multiscale method. The solution is asymptotic with respect to a small dimensionless parameter, ϵ, which is defined as the ratio of a mean-free-path to the diameter of the medium. The leading term of the solution is the product of two functions, one determined by a cell calculation and the other as the solution of a diffusion equation. The coefficients in the diffusion equation contain functions that are determined by cell calculations ard are then averaged over the cell. We compare the asymptotic diffusion coefficients to other “homogenized” dif usion coefficients that have been proposed in the literature and show that a substantial numerical disagreement exists for a large class of problems. We also give a physical interpretation to the asymptotic solution and to the numerical results concerning the asymptotic diffusion coefficients.