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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.
S. Rauck, R. Sanchez, I. Zmijarevic, M. Nobile
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 73-83
Technical Paper | doi.org/10.13182/NSE00-A2126
Articles are hosted by Taylor and Francis Online.
Through the introduction of appropriate boundary conditions, the use of multigroup albedos permits one to concentrate the numerical effort of solving the transport equation in only the domain of interest, thus reducing computational requirements. Multigroup albedos that are representative of an external medium can be calculated via independent transport calculations and collapsed for use in a few-group three-dimensional transport calculation. The multigroup albedo method is developed and applied to the calculation of the Orphée research reactor. Numerical comparisons between full-core two-dimensional transport calculations and two-dimensional transport calculations performed with multigroup albedos show why the method is interesting. The axial power distribution obtained from a three-dimensional transport calculation with multigroup albedos precisely matches measured experimental values, while results from three-dimensional full-core diffusion calculations give unacceptable errors.