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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.
T. H. Fanning, G. Palmiotti
Nuclear Science and Engineering | Volume 127 | Number 2 | October 1997 | Pages 154-168
Technical Paper | doi.org/10.13182/NSE97-A28594
Articles are hosted by Taylor and Francis Online.
The variational nodal transport method is generalized for the treatment of heterogeneous nodes while maintaining nodal balances. Adapting variational methods to heterogeneous nodes requires the ability to integrate over a node with discontinuous cross sections. Integrals are evaluated using composite Gaussian quadrature rules, which permit accurate integration while yielding acceptable computing times. Allowing structure within a nodal solution scheme avoids some of the necessity of cross-section homogenization and more accurately defines the intranodal flux shape. Ideally, any desired heterogeneity can be constructed within the node, but in reality, the finite set of basis functions limits the intranodal complexity that can be modeled. Comparison tests show that the heterogeneous variational nodal method provides accurate results for moderate heterogeneities, even if some improvements are needed for very difficult configurations.