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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
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 358-368
Technical Paper | doi.org/10.13182/NSE96-A24199
Articles are hosted by Taylor and Francis Online.
The integral transport equation is solved in square unit cells by assuming the existence of a fundamental mode. The equations governing the Bn method are given without making the small buckling approximation. First, the angular flux is factorized into two parts: a periodic microscopic fine-structure 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 fine-structure flux, is obtained using collision probability calculations that are repeated until criticality is achieved. The procedure allows the periodic or reflective boundary conditions of the unit cell to be taken into account using closed-form contributions obtained from the cyclic tracking technique. Numerical results are presented for one-group heterogeneous cell problems with isotropic and linearly anisotropic scattering kernels, some of which include void regions.