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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. Santandrea, R. Sanchez, P. Mosca
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 23-40
Technical Paper | doi.org/10.13182/NSE07-69
Articles are hosted by Taylor and Francis Online.
The method of characteristics (MOC) in unstructured meshes has become a standard for reactor physics applications. One of the major drawbacks of the MOC is the difficulty to implement higher-order integration schemes to improve spatial convergence. In this paper we present a high-order MOC spatial discretization that uses linear interpolation on surface values for the collision source. This conservative linear surface (CLS) scheme exhibits parabolic convergence with the mesh size but lacks positivity. Numerical results for the well-known Stepanek benchmark and for more realistic boiling water reactor assemblies show CLS faster convergence over the standard step characteristics scheme. A generalization of the synthetic DPN acceleration scheme provides an efficient method to accelerate the internal transport iterations.