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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.
R. Roy, A. Hébert, G. Marleau
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 112-128
Technical Paper | doi.org/10.13182/NSE93-A28522
Articles are hosted by Taylor and Francis Online.
The integral transport equation is solved in periodic slab lattices in the case where a critical buckling search is performed. First, the angular flux is factorized into two parts: a periodic microscopic flux and a macroscopic form with no angular dependence. The macroscopic form only depends on a buckling vector with a given orientation. The critical buckling norm along with the corresponding microscopic flux are obtained using anisotropic collision probability calculations that are repeated until criticality is achieved. This procedure allows the periodic boundary conditions of slab lattices to be taken into account using closed-form contributions obtained from the cyclic-tracking technique, without resorting to infinite series of exponential-integral evaluations. Numerical results are presented for one-group heterogeneous problems with isotropic and anisotropic scattering kernels, some of which include void slit regions.