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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.
E. A. Fischer
Nuclear Science and Engineering | Volume 78 | Number 3 | July 1981 | Pages 227-238
Technical Paper | doi.org/10.13182/NSE81-A20300
Articles are hosted by Taylor and Francis Online.
An approximate method to calculate the parallel neutron leakage in fast reactor slab lattices is described. It is derived from the integral transport equation and assumes isotropic scattering. By using an expansion in terms of oscillating functions, rather than the usual power series expansion in the buckling, it is proven that the method is also valid for voided cells. Results for a two-region cell are presented; they confirm that the widely used Benoist equation is valid for cases when sodium is present. However, for voided or nearly voided cells, the Benoist equation fails, whereas the new method is valid for any cell composition. The same method is applied to find the effective diffusion coefficient for a low-density channel. In the limit of zero buckling, the method reduces to well-known results available in literature by Rowlands. However, the buckling correction, obtained by a consistent expansion of the integral transport equation, is different from similar corrections in the literature.