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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.
A. Hébert, G. Mathonnière
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 129-141
Technical Paper | doi.org/10.13182/NSE115-129
Articles are hosted by Taylor and Francis Online.
Proposals are made for improving current second-generation superhomogénéisation (SPH) methods in three different ways and to use them in heterogeneous and homogeneous diffusion procedures for reactor design and operating calculations. The first improvement consists of using a surface radial leakage model in the flux calculation to represent the macroscopic flux curvature in the assembly. The second improvement is accomplished by the introduction of the Selengut normalization in the SPH equivalence procedure replacing the flux-volume normalization currently used with second-generation methods. Finally, the buckling calculation is improved to better represent the target color-set. Second- and third-generation SPH techniques for heterogeneous or homogeneous diffusion procedures are now implemented as a unified algorithm in a lattice code. Two-group benchmarks are proposed to measure precisely the equivalence effectiveness and the improvement gained with third-generation methods.